Nuclear reactor and method for autonomously controlling such nuclear reactor

Abstract

A nuclear reactor for maintaining a continuous nuclear fission chain reaction, the nuclear reactor comprising a vessel (1) having an interior (30, 35), the nuclear reactor further comprising in the interior of the vessel: a nuclear reactor core (2); a primary heat exchange circuit (3); a conduit (23) for transporting the internal and external heat exchange medium; a heat exchange device for exchanging heat between the primary heat exchange medium and the internal and external heat exchange media; and at least one controller (50) configured to autonomously control the operation of the nuclear reactor in dependence on data originating within the vessel (1).

Description

Technical Field

[0001] The present disclosure relates to nuclear reactors and methods of controlling such nuclear reactors, and more particularly to the construction and design of a nuclear reactor under autonomous control and a method of autonomously controlling such a nuclear reactor. Background Art

[0002] The most common nuclear reactors are large and complex pressurized water reactors (PWRs) or boiling water reactors (BWRs). Both PWRs and BWRs use ordinary water as both coolant and moderator and typically rely on active systems, such as backup diesel generators, to ensure safety, that is, these reactors are not inherently safe. These nuclear reactors are controlled by a team of human operators from a control room. The complexity of these nuclear reactors, the complexity of their control, and the involvement of multiple human operators in controlling the nuclear reactors result in high operating costs for these common nuclear reactors and also leave room for improvement in safety and reliability.

[0003] Many advanced nuclear reactor types can achieve passive safety, making their operation not require active backup systems. Such reactors are generally considered safer than traditional reactors such as PWRs and BWRs because they do not rely on human or machine intervention to safely shut down the reactor in an emergency. Passive safety reactor concepts have been proposed in different reactor categories, including molten salt reactors (MSRs), high-temperature gas-cooled reactors, liquid metal-cooled solid fuel reactors, and some advanced water reactors.

[0004] The main safety function of a nuclear reactor is to prevent the release of radionuclides during normal operation, shutdown, or accident conditions. Part of the role of human nuclear operators is often to ensure control of the reactor to prevent the release of radionuclides. There is a desire to develop new reactor concepts that can achieve this function without human intervention but rely on safety inherent in the design.

[0005] A molten salt reactor (MSR) is a nuclear reactor in which the nuclear reactor coolant and / or nuclear fuel is a molten salt, typically a fluoride salt or a chloride salt, having a melting point of about ~500 °C, an operating temperature of about ~600 °C to 700 °C, and a boiling point higher than the melting point by ~1000 °C. One of the many advantages of this type of reactor is that the molten salt can be used as a heat transfer medium at very high temperatures while still being able to operate at or near atmospheric pressure. Heat is extracted from such a reactor by pumping the molten salt in a loop or by natural convection between the nuclear reactor core and a heat exchanger, where the reactor power is proportional to the temperature drop across the heat exchanger and the flow rate. Since the molten salt reactor has a large negative temperature and void coefficient, the molten salt reactor can be designed and constructed to be inherently self-regulating and have passive decay heat removal, and is thus referred to as inherently safe.

[0006] JP2016176821A discloses a nuclear reactor having a monitoring unit that monitors the operation of the nuclear reactor using a thermoacoustic sensor in the nuclear reactor core.

[0007] WO2021141882 discloses a sensor assembly for determining operating characteristics of a nuclear reactor. The sensor assembly includes a solid-state laser medium doped with a fissionable material and capable of being placed within the nuclear reactor core, and an optical fiber operatively coupled to the solid-state laser medium and configured to extend out of the nuclear reactor core and into the control system of the nuclear reactor. The fissionable material includes one or more of uranium, plutonium, americium, or californium. A method for determining operating characteristics of a nuclear reactor includes: during operation of the nuclear reactor, receiving laser light from the optical fiber, analyzing the laser light, and determining the operating characteristics of the nuclear reactor based on the analysis of the laser light.

[0008] In order to enable large-scale deployment of nuclear reactors, it is desirable to reduce their deployment costs and improve their safety and reliability. SUMMARY OF THE INVENTION

[0009] It is an object to provide a nuclear reactor that can overcome or at least reduce one of the above problems.

[0010] The foregoing and other objects are achieved by the features of the independent claims. Further implementations are apparent from the dependent claims, the description, and the drawings.

[0011] According to a first aspect, there is provided a nuclear reactor for maintaining a sustained nuclear fission chain reaction, the nuclear reactor including an enclosed container, preferably, the nuclear reactor including an enclosed and sealed leak-tight container having an interior, the interior of the container containing:

[0012] a nuclear reactor core;

[0013] At least a primary heat exchange circuit, said primary heat exchange circuit including a primary heat exchange medium pump for circulating a primary heat exchange medium in said primary heat exchange circuit;

[0014] A pipe for transporting internal and external heat exchange media, said pipe fluidly connecting an inlet and an outlet;

[0015] Said inlet penetrates the exterior of the container, and said outlet penetrates the exterior of the container;

[0016] A heat exchange device for exchanging heat between the primary heat exchange medium and the internal and external heat exchange media; and

[0017] At least one controller configured to autonomously control the operation of a nuclear reactor depending on data originating within the container;

[0018] At least some of the data originating within the container originates from one or more sensors arranged within the container. Preferably, the data originating within the container includes at least one thermodynamic condition of the primary heat exchange medium.

[0019] By providing a controller for the nuclear reactor that autonomously controls the operation of the nuclear reactor depending on data originating within the container, preferably the controller autonomously controls the operation of the nuclear reactor only depending on data originating within the container, a nuclear reactor is provided that requires no external or human operation, which significantly reduces the operating cost and improves the safety of the nuclear reactor. The resulting nuclear reactor is inherently very simple, neither requiring nor accepting data input from external computers or sensors, which are easily manipulated by malicious actors, thus significantly improving the safety and reliability of the reactor operation and reducing the operating cost. The inherent safety of the reactor means that the controller is non-safety-critical and its function is not critical to the operation of the reactor.

[0020] In a possible form of interpretation of the first aspect, a closed and preferably leak-tight container contains all components of the reactor, wherein the only penetrations of the container are the inlet and outlet openings for the internal and external heat exchange media and the electrical connection for supplying power to the components within the closed container.

[0021] In a possible implementation form of the first aspect, the reactivity of the nuclear reactor is controlled by closed-loop control, wherein the sensed process variable is the thermodynamic condition of the primary heat exchange medium sensed by sensors within the container, such as temperature sensors or radiation sensors, and transmitted to at least one controller.

[0022] In a possible implementation form of the first aspect, the at least one controller is configured to maintain the operating parameters of the nuclear reactor within one or more specified ranges, thereby allowing the heat generated by the nuclear reactor core during at least the normal operation of the nuclear reactor to be transferred through the internal and external heat exchange media in the heat exchange device, and / or allowing the regulation of the nuclear fission chain reaction in the nuclear reactor.

[0023] In a possible implementation form of the first aspect, at least one controller is configured to autonomously control the operation of the nuclear reactor relying only on data originating within the vessel.

[0024] In a possible implementation form of the first aspect, the nuclear reactor operates according to an inherently safe process that directly provides passive safety components under specific fault conditions in all operating modes.

[0025] In a possible implementation form of the first aspect, the nuclear reactor does not require any active intervention or electrical / electronic feedback on the part of the operator to bring the reactor into a safe shutdown state.

[0026] In a possible implementation form of the first aspect, the nuclear reactor is inherently safe, and preferably, the nuclear reactor does not rely on active systems to ensure the safety of the reactor.

[0027] In a possible implementation form of the first aspect, the at least one controller is configured to control the power output of the nuclear reactor core by adjusting the ongoing nuclear fission chain reaction. Preferably, the at least one controller is configured to control the power output of the nuclear reactor core by adjusting the level of the liquid neutron moderator in the reactor core.

[0028] In a possible implementation form of the first aspect, the at least one controller is configured to control the power output of the nuclear reactor core by adjusting the height or position of control rods within or near the reactor core.

[0029] In a possible implementation form of the first aspect, at least one controller is configured to control the power output of the nuclear reactor core as a function of the power absorbed by the internal and external heat exchange media in the heat exchange device. Preferably, the function is one that ensures that the power output of the nuclear reactor core is substantially equal to the power absorbed by the internal and external heat exchange media in the heat exchange device. Preferably, the function is the following function: taking into account the heat transferred away from the nuclear reactor core in other ways, such as the heat lost through the decay heat removal system during normal operation and / or the heat lost to the liquid moderator or solid moderator coolant, and ensuring that the power output of the nuclear reactor core is substantially equal to the power absorbed by the internal and external heat exchange media in the heat exchange device.

[0030] In a possible implementation form of the first aspect, at least one controller is configured to adjust the flow rate of the primary coolant, for example, by instructing the driver to control the speed of the electric motor driving the primary pump to adjust the speed of the primary pump. In a molten salt reactor, assuming that the coolant temperature remains constant, adjusting the flow rate of the primary coolant indirectly affects the reactivity.

[0031] In a possible implementation form of the first aspect, one or more of the heat exchange media in the heat exchange medium are driven by natural convection rather than being pumped, and operate passively or are controlled by throttling, for example, through a valve.

[0032] In a possible implementation form of the first aspect, at least one controller is configured to maintain the temperature of the primary heat exchange medium at one or more given positions in the primary circuit at a specified temperature or within a specified temperature range.

[0033] In a possible implementation form of the first aspect, the at least one controller is configured to adjust the speed of the primary pump. Preferably, the at least one controller is configured to adjust the speed of the primary pump as a function of at least one thermodynamic condition of the primary heat exchange medium. Preferably, the at least one thermodynamic condition is derived from one or more sensors arranged in the container. Preferably, the function includes one or more of a proportional part, an integral part, and a derivative part, and / or the at least one controller 50 includes a model predictive controller.

[0034] In a possible implementation form of the first aspect, at least one thermodynamic condition of the primary heat exchange medium includes the temperature of the primary heat exchange medium sensed by the temperature sensors 9, 9' arranged inside or its derivative.

[0035] In a possible implementation form of the first aspect, the temperature sensor is arranged in a thermocouple sleeve (insert thermocouple sleeve) or mounted on the tube surface.

[0036] In a possible implementation form of the first aspect, the at least one controller includes one or more of analog electronics, digital electronics, software for processing electronic values, mechanical logic, hydraulic and / or fluid logic. Preferably, the at least one controller does not include an electronic digital programmable computer. Preferably, the at least one controller uses a redundant architecture. Even more preferably, the at least one controller uses different redundant architectures.

[0037] In a possible implementation form of the first aspect, the nuclear reactor includes a circuit breaker device, and the circuit breaker device is configured to connect at least one of the electrical components and / or electronic components inside to a power source within the container and to disconnect at least one of the electrical components and / or electronic components inside from the power source within the container. Preferably, the circuit breaker device includes a circuit breaker, and the circuit breaker is controlled by one of the at least one controller. Preferably, the nuclear reactor is configured to end the nuclear reaction and enter a safe state when disconnecting at least one of the electrical components and / or electronic components inside from the power source.

[0038] The circuit breaker circuit is relatively simple and very robust. By using the circuit breaker circuit, a reliable and robust system can be provided to shut down the reactor when needed. The inherent safety of the reactor and the shutdown of the reactor through the circuit breaker circuit mean that the controller is not safety-critical and its function is not crucial for the operation of the reactor.

[0039] In a possible implementation form of the first aspect, the at least one controller is configured to start the operation of the nuclear reactor by connecting the electrical components and / or electronic components to the power source by switching the circuit breaker device from the open position to the closed position.

[0040] In a possible implementation form of the first aspect, the at least one controller is configured to end the operation of the nuclear reactor by connecting the electrical components and / or electronic components to the power source by switching the circuit breaker device from the open position to the closed position.

[0041] In a possible implementation form of the first aspect, the circuit breaker device includes a circuit breaker and one of the at least one controller. Preferably, one of the at least one controller includes analog electronics and / or digital electronics, and the analog electronics and / or digital electronics are configured to operate the circuit breaker in an open or closed manner. Preferably, one of the at least one controller does not include an electronic digital programmable computer.

[0042] In a possible implementation form of the first aspect, the nuclear reactor is a molten salt nuclear reactor, the primary heat exchange medium is a fuel salt containing fissile material, the primary heat exchange medium circuit is a fuel salt circuit, the primary heat exchange medium pump is a fuel salt pump, the heat exchange device includes a primary heat exchanger, and the primary heat exchange circuit passes through the primary heat exchanger. And preferably, at least one thermodynamic condition includes one or more of the following:

[0043] The fuel salt temperature or its derivative at a position between the outlet of the primary heat exchanger and the fuel salt inlet of the nuclear reactor core;

[0044] The fuel salt temperature or its derivative at a position between the fuel salt outlet of the nuclear reactor core and the inlet of the primary heat exchanger;

[0045] The fuel salt flow rate, preferably, the fuel salt flow rate is derived according to the rotational speed of the primary pump.

[0046] In a possible implementation form of the first aspect, the molten salt reactor is designed and configured to be inherently self-regulating, and has passive decay heat removal, and preferably is inherently safe.

[0047] In a possible implementation form of the first aspect, the interior includes a primary cooling salt circuit that passes through the primary heat exchanger to exchange heat with the fuel salt, and preferably, the primary cooling salt circuit passes through the primary heat exchanger to exchange heat with the fuel salt and the primary cooling salt circuit passes through the secondary heat exchanger to exchange heat with the internal and external heat exchange media. The primary cooling salt circuit includes a secondary pump that is used to circulate the primary cooling salt in the primary cooling salt circuit, and preferably, the at least one thermodynamic condition includes one or more of the following:

[0048] The primary cooling salt temperature or its derivative at a position between the outlet of the secondary heat exchanger and the primary cooling salt inlet of the primary heat exchanger;

[0049] The primary cooling salt temperature or its derivative at a position between the primary cooling salt outlet of the primary heat exchanger and the inlet of the secondary heat exchanger;

[0050] The primary cooling salt flow rate, preferably, the primary cooling salt flow rate is derived according to the rotational speed of the secondary pump 14.

[0051] In a possible implementation form of the first aspect, the interior includes a moderator device that is used to adjust the moderation level in the nuclear reactor core, and at least one controller is configured to control the moderation level in the nuclear reactor core as a function of data originating within the vessel.

[0052] In a possible implementation form of the first aspect, the liquid moderator and neutron reflector are heavy water or molten hydroxides, preferably molten hydroxides of molten lithium-7 deuterium oxide (7LiOD).

[0053] In a possible implementation form of the first aspect, a liquid moderator circuit is included inside, and the liquid moderator circuit includes a moderator pump for circulating a liquid moderator in the moderator circuit. The liquid moderator circuit passes through the nuclear reactor core. Preferably, the liquid moderator circuit passes through the nuclear reactor core and through a liquid moderator heat exchanger. Wherein, preferably, the at least one thermodynamic condition includes one or more of the following:

[0054] The temperature of the liquid moderator at a position between the liquid moderator outlet of the liquid moderator heat exchanger and the liquid moderator inlet of the nuclear reactor core;

[0055] The temperature of the liquid moderator at a position between the liquid moderator outlet of the nuclear reactor core 2 and the liquid moderator inlet of the liquid moderator heat exchanger;

[0056] The liquid moderator flow rate. Preferably, the liquid moderator flow rate is obtained according to the rotational speed of a three-stage pump.

[0057] In a possible implementation form of the first aspect, the at least one controller is configured to provide an output value, and the output value includes one or more of the following:

[0058] - The speed of the primary pump,

[0059] - The speed of the secondary pump,

[0060] - The speed of the three-stage pump,

[0061] - The speed of the liquid moderator pump,

[0062] - The speed of the blanket salt pump,

[0063] - The end of operation of the primary pump,

[0064] - The end of operation of the secondary pump,

[0065] - The end of operation of the three-stage pump,

[0066] - The end of operation of the liquid moderator pump,

[0067] - The end of operation of the blanket salt pump,

[0068] - The start of operation of the primary pump,

[0069] - The start of operation of the secondary pump,

[0070] - The start of operation of the three-stage pump,

[0071] - The start of operation of the liquid moderator pump,

[0072] - The start of operation of the blanket salt pump.

[0073] In a possible implementation of the first aspect, the at least one controller includes analog electronics, digital electronics, and one or more of software, mechanical logic, and hydraulic logic for processing electronic values, and preferably, the at least one controller does not include an electronic digital programmable computer.

[0074] In a possible implementation of the first aspect, the nuclear reactor is a molten salt reactor, and the at least one controller is configured to perform one or more of the following:

[0075] - Adjust the primary pump speed to maintain the fuel salt temperature at the reactor core outlet at approximately 700 °C. Preferably, adjusting the primary pump speed includes reducing the primary pump speed to increase the fuel salt temperature at the fuel salt outlet, and increasing the primary pump speed to reduce the fuel salt temperature at the reactor core outlet.

[0076] - Adjust the tertiary pump speed to adjust the liquid moderator level in the nuclear reactor core and thus adjust the reactivity to maintain the average fuel salt temperature between the reactor core inlet and the reactor core outlet fuel salt at approximately 650 °C. Preferably, adjusting the tertiary pump speed includes increasing the moderator pump speed to increase the reactivity and the average temperature in the reactor core, and reducing the moderator pump speed to reduce the reactivity and the average fuel salt temperature in the reactor core.

[0077] - Adjust the secondary pump speed to maintain the fuel salt temperature at the reactor core inlet at approximately 600 °C. Preferably, adjusting the secondary pump speed includes increasing the secondary pump speed to reduce the fuel salt temperature at the fuel salt inlet, and reducing the secondary pump speed to increase the fuel salt temperature at the fuel salt inlet.

[0078] - Adjust the moderator coolant pump speed to maintain the temperature of the liquid moderator at the liquid moderator outlet of the nuclear reactor core at approximately 20 °C. Preferably, adjusting the moderator coolant pump speed includes increasing the moderator coolant pump speed to reduce the temperature of the liquid moderator at the liquid moderator outlet of the nuclear reactor core, and reducing the moderator coolant pump speed to increase the temperature of the liquid moderator at the liquid moderator outlet of the nuclear reactor core.

[0079] In a possible implementation of the first aspect, the at least one controller is a controller with proportional, integral, and / or derivative parts (PID controller), and / or the at least one controller operates as a model predictive controller.

[0080] In a possible implementation form of the first aspect, a driver is provided at each pump in the interior, and the driver receives a pump rotation speed signal from at least one controller. Preferably, each driver is supplied with power through a circuit breaker, and when the circuit breaker trips (switches), the pump is shut down.

[0081] In a possible implementation form of the first aspect, the interior includes an uplink transmitter configured to transmit data from the controller to an external receiver, and preferably, the uplink transmitter is configured to allow only unidirectional transmission, that is, only transmission from the transmitter to a receiver outside the container.

[0082] In a possible implementation form of the first aspect, the data originating from within the container includes one or more of the following:

[0083] - The neutron radiation level in the interior of the container, preferably, the neutron radiation level in the interior of the container from a radiation sensor arranged in the interior.

[0084] - Seismic data from a seismic sensor arranged in the interior of the container.

[0085] - The temperature of the covering salt at the covering salt inlet of the nuclear reactor core, and the covering salt loop in the interior includes a covering salt pump for circulating the covering cooling salt in the covering salt loop.

[0086] - The temperature of the covering salt at the covering salt outlet of the nuclear reactor core, and the covering salt loop in the interior includes a covering salt pump for circulating the covering cooling salt in the covering salt loop.

[0087] - The temperature of the gas filling the space in the interior of the container. If the interior includes a hot zone and a cold zone, the temperature of the gas filling the space in the interior of the container is the temperature of the gas filling the space in the hot zone.

[0088] - Signals from a leak detector associated with one or more of the following:

[0089] - The primary heat exchange loop.

[0090] - Pipelines.

[0091] - The secondary heat exchange loop.

[0092] - The tertiary heat exchange loop.

[0093] - The liquid moderator loop.

[0094] - The liquid moderator coolant loop.

[0095] - The covering salt loop.

[0096] - A signal from a sensor indicating an open position and / or a closed position of a door in a container to access the interior.

[0097] In a possible implementation form of the first aspect, the fuel salt is a fluoride salt with a melting point of about 550 °C, the primary coolant salt is a fluoride salt or a chloride salt with a melting point of about 450 °C, preferably, the covering salt is a fluoride salt with a melting point of about 550 °C, preferably, the scrubber salt is a fluoride salt with a melting point of about 550 °C, preferably, the second coolant salt is a nitrate with a melting point of about 250 °C and a decomposition temperature of about 570 °C.

[0098] In a possible implementation form of the first aspect, one of the at least one controllers is configured to open one or more circuit breakers when one or more of the following conditions are not met:

[0099] - The leak detection sensor shows no leak,

[0100] - The radiation level is below the radiation threshold,

[0101] - The derivative of the radiation level is below the derivative radiation threshold,

[0102] - The internal hot zone is between about 580 °C and about 720 °C,

[0103] - The fuel salt inlet temperature is between about 580 °C and about 720 °C,

[0104] - The fuel salt outlet temperature is between about 580 °C and about 720 °C,

[0105] - The primary coolant salt inlet temperature is between about 480 °C and about 720 °C,

[0106] - The primary coolant salt outlet temperature is between about 480 °C and about 720 °C,

[0107] - The second coolant salt inlet temperature is between about 300 °C and about 570 °C,

[0108] - The second coolant salt outlet temperature is between about 300 °C and about 570 °C,

[0109] - The covering salt inlet temperature is between about 580 °C and about 720 °C,

[0110] - The covering salt outlet temperature is between about 580 °C and about 720 °C,

[0111] - The scrubber salt inlet temperature is between about 580 °C and about 720 °C,

[0112] - The scrubber salt outlet temperature is between approximately 580 °C and approximately 720 °C,

[0113] - The liquid moderator inlet temperature is between approximately 5 °C and approximately 90 °C,

[0114] - The liquid moderator outlet temperature is between approximately 5 °C and approximately 90 °C,

[0115] - The liquid moderator coolant inlet temperature is between approximately 5 °C and approximately 90 °C,

[0116] - The liquid moderator coolant outlet temperature is between approximately 5 °C and approximately 90 °C.

[0117] In a possible implementation form of the first aspect, one of the at least one controllers is configured to close the circuit breaker in the absence of conditions requiring the circuit breaker to open.

[0118] In a possible implementation form of the first aspect, the controller includes a time delay for starting the pump after the circuit breaker is opened, such that in the case where the circuit breaker is triggered only for a short time (as in the case of a transient scenario), all the liquid can be fully drained back into the tank before restarting.

[0119] In a possible implementation form of the first aspect, the interior of the container includes a hot zone and a cold zone. The hot zone includes: a nuclear reactor core; a primary heat exchange loop, the primary heat exchange loop including a primary pump; pipes for internal and external heat exchange media; and a heat exchange device, the heat exchange device including at least a primary heat exchanger for exchanging heat between the primary exchange medium and the internal and external heat exchange media, and preferably including a primary heat exchange medium dump tank, and preferably, the cold zone houses electronic devices, breaker circuits, and other heat-sensitive components, electronic devices, sensors.

[0120] In a possible implementation form of the first aspect, the interior of the container includes a hot zone and a cold zone separated by thermal insulation material and / or radiation shielding material to minimize heat loss from the cold zone and the cooling requirements for the cold zone and / or to minimize the radiation exposure of electronic devices, breaker circuits, and other radiation-sensitive components, electronic devices, sensors.

[0121] In a possible implementation form of the first aspect, each heat exchange loop included in the interior has an associated dump tank and pump, the pump being configured to lead to the liquid when stopped to allow all the heat exchange medium in the corresponding heat exchange medium loop to be drained into the dump tank associated with the corresponding heat exchange loop when the pump associated with the corresponding heat exchange loop stops. Preferably, the dump tank is configured to allow the decay heat of the radionuclides in the corresponding liquid to be passively transferred through the reactor vessel when the corresponding heat exchange medium is contained in the corresponding dump tank.

[0122] In a possible implementation of the first aspect, the interior includes critical sensors and non-critical sensors, each critical sensor having at least one operating threshold, and at least one controller being configured to open a circuit breaker associated with the critical sensor when the operating threshold associated with the relevant critical sensor is exceeded.

[0123] In a possible implementation of the first aspect, the critical sensors and non-critical sensors include one or more of the following: inserted thermocouples, liquid leak detection sensors, radiation monitors. Preferably, the critical sensors and / or non-critical sensors provide redundancy by having multiple components thereof and processing the outputs of these multiple components and using the consistency of the multiple components, preferably by one or more of analog electronics, software for processing electronic values, or mechanical logic, hydraulic and / or fluid logic. Preferably, Boolean algorithms are used to ensure that the failure of one or more critical sensors or non-critical sensors does not cause incorrect values to be used by at least one controller.

[0124] In a possible implementation of the first aspect, wherein the salt temperature is sensed by a first temperature sensor (preferably an inserted thermocouple) to provide a signal for maintaining the temperature to the controller 50, and wherein a second image sensor (preferably an inserted thermocouple) is provided to send a signal to the breaker circuit.

[0125] In a possible implementation of the first aspect, the liquid moderator is heavy water.

[0126] In a possible implementation of the first aspect, the liquid moderator is heavy water, and there is also hydroxide or deutoxide, preferably enriched lithium-7 deutoxide (7LiOD), and preferably a eutectic mixture to lower the melting point of the heavy water and enable the liquid moderator to operate below 0 °C and make the thermal neutron spectrum colder.

[0127] In a possible implementation of the first aspect, the fuel salt includes fission components. Preferably, the fuel salt includes fission components enriched in lithium-7 fluoride, thorium tetrafluoride, uranium tetrafluoride, uranium trifluoride, and / or plutonium trifluoride (7LiF)-(ThF4)-(UF4)-(UF3)-(PuF3) salts.

[0128] In a possible implementation of the first aspect, the fuel salt contains fission components. Preferably, the fuel salt includes fission components enriched in lithium-7 fluoride, uranium tetrafluoride, depleted uranium trifluoride (7LiF)-(UF4)-(UF3) salts.

[0129] In a possible implementation form of the first aspect, the blanket salt is a molten salt containing a proliferable component. Preferably, the blanket salt is a molten salt containing a molten salt rich in lithium heptafluoride and / or thorium tetrafluoride ((7LiF)-(ThF4)).

[0130] According to a second aspect, there is provided a method of operating a nuclear reactor according to any one of the preceding claims, the method comprising determining the power output of a molten salt nuclear reactor by controlling the amount of power absorbed by the internal and external heat exchange media flowing through the heat exchange medium pipes. Preferably, the method comprises determining the power output of a molten salt nuclear reactor by controlling the flow rates of the internal and external heat exchange media flowing through the pipes.

[0131] By providing a method in which the power output of a nuclear reactor automatically adapts to the amount of power absorbed by the internal and external heat exchange media, the power output of the nuclear reactor can be controlled by controlling the power removed from the nuclear reactor by a heat consumption device. Thus, neither an external controller is required to send a power setting signal to the nuclear reactor, nor is any other external signal required to be sent to the nuclear reactor or the human operator of the reactor.

[0132] By providing a method of controlling an inherently safe nuclear reactor, and the nuclear reactor includes a breaker circuit that depends on data originating within the vessel. Preferably, the breaker circuit depends only on data originating within the vessel, and the breaker circuit controller has specific limitations, such as thermodynamic conditions or states, for which the reactor is considered to be operating safely. The reactor can be operated by a non-safety-critical controller without the risk of radioactive nuclide release because any exceeded limitation will cause the breaker circuit to switch, thereby shutting down the reactor. Thus, neither an external controller is required to send a shutdown or startup signal to the nuclear reactor, nor is any other external signal required to be sent to the nuclear reactor or the human operator of the reactor. In addition, no human participation is required, thereby eliminating the risk of human error, which is a safety benefit, and this method of controlling a nuclear reactor reduces the possible attack vectors, which is also a safety benefit.

[0133] According to a third aspect, there is provided a method of operating a nuclear reactor that sustains a continuous nuclear fission chain reaction, the nuclear reactor including a closed vessel. Preferably, the nuclear reactor includes a closed and leak-tight vessel having an interior, and the interior of the vessel contains:

[0134] A nuclear reactor core;

[0135] At least a primary heat exchange loop including a primary heat exchange medium pump for circulating a primary heat exchange medium through the primary heat exchange loop; and

[0136] A pipe for transporting internal and external heat exchange media, the pipe fluidly connecting an inlet and an outlet;

[0137] The inlet penetrates the exterior of the container, and the outlet penetrates the exterior of the container;

[0138] A heat exchange device for exchanging heat between a primary heat exchange medium and the internal and external heat exchange media;

[0139] The method includes autonomously controlling the operation of the nuclear reactor depending on data originating within the container. Preferably, the method includes autonomously controlling the operation of the nuclear reactor depending only on data originating within the container, and at least some of the data originating within the container originates from one or more sensors arranged within the container. Preferably, the data originating within the container includes at least one thermodynamic condition of the primary heat exchange medium.

[0140] According to a fourth aspect, there is provided a nuclear reactor for maintaining a sustained nuclear fission chain reaction, the nuclear reactor including a container having a hermetically sealed interior containing: a nuclear reactor core; a primary heat exchange loop; a pipe for transporting internal and external heat exchange media; a heat exchange device for exchanging heat between the primary heat exchange medium and the internal and external heat exchange media; and at least one controller configured to autonomously control the operation of the nuclear reactor depending on data originating within the container. Preferably, the at least one controller is configured to autonomously control the operation of the nuclear reactor depending only on data originating within the container.

[0141] According to a fifth aspect, there is provided a nuclear reactor for maintaining a sustained nuclear fission chain reaction, the nuclear reactor including an enclosed container. Preferably, the nuclear reactor includes an enclosed and hermetically sealed container having an interior containing:

[0142] A nuclear reactor core;

[0143] At least a primary heat exchange loop including a primary heat exchange medium pump for circulating a primary heat exchange medium in the primary heat exchange loop;

[0144] At least one sensor configured to provide a signal indicative of the operating state of the nuclear reactor;

[0145] A circuit breaker device, the circuit breaker device including a circuit breaker, the circuit breaker device being configured to connect at least one of the electrical components and / or electronic components in the interior to a power source within the container and to disconnect at least one of the electrical components and / or electronic components in the interior from the power source within the container, the circuit breaker device including a circuit breaker having an open state and a closed state, the circuit breaker device being connected to at least one sensor, and the circuit breaker being configured to open the circuit breaker when a signal from the at least one sensor exceeds a safety threshold, preferably, the safety threshold being a safety threshold indicating that the nuclear reactor is operating in a scram mode, a critical component has failed, or another safety-critical threshold has been exceeded.

[0146] By providing a circuit breaker device triggered by a signal sensor configured to provide a signal representing the operating state of a nuclear reactor, a nuclear reactor can be created that can automatically shut down in a safe manner without human intervention when the reactor approaches or reaches an unsafe state, thereby significantly reducing the risk of human error.

[0147] In a possible implementation form of the fifth aspect, the electrical component and / or electronic component includes an electric motor for driving a primary exchange pump.

[0148] In a possible implementation form of the fifth aspect, the at least one sensor includes a sensor configured to sense the temperature of the primary heat exchange medium.

[0149] In a possible implementation form of the fifth aspect, the nuclear reactor is configured to end the nuclear reaction and enter a safe state when disconnecting at least one of the electrical components and / or electronic components in the interior from the power source.

[0150] In a possible implementation form of the fifth aspect, the nuclear reactor is configured to start operating when the electrical component and / or electronic component is connected to the power source, preferably, the nuclear reactor is configured to start operating when the electrical component and / or electronic component is connected to the power source by switching the circuit breaker device from the open position to the closed position.

[0151] In a possible implementation form of the fifth aspect, the nuclear reactor is configured to end operation by disconnecting the electrical component and / or electronic component from the power source, preferably, the nuclear reactor is configured to end operation by disconnecting the electrical component and / or electronic component from the power source by switching the circuit breaker device from the open position to the closed position.

[0152] In a possible implementation form of the fifth aspect, the circuit breaker device includes a circuit breaker and a controller. Preferably, the controller includes analog electronic devices and / or digital electronic devices, and the analog electronic devices and / or digital electronic devices are configured to operate the circuit breaker in an open mode or a closed mode. Preferably, one of the at least one controllers does not include an electronic digital programmable computer.

[0153] In a possible implementation form of the fifth aspect, the nuclear reactor is a molten salt nuclear reactor, the primary heat exchange medium is a fuel salt containing fissile material, the primary heat exchange medium circuit is a fuel salt circuit, the primary heat exchange medium pump is a fuel salt pump, the heat exchange device includes a primary heat exchanger, the primary heat exchange circuit passes through the primary heat exchanger, and wherein at least one sensor includes one or more of the following:

[0154] A fuel salt temperature sensor located at a position between the outlet of the primary heat exchanger and the fuel salt inlet of the nuclear reactor core;

[0155] The fuel salt temperature at a position between the fuel salt outlet of the nuclear reactor core and the inlet of the primary heat exchanger;

[0156] A fuel salt flow sensor. Preferably, the fuel salt flow is derived from the rotational speed of the primary pump.

[0157] In a possible implementation form of the fifth aspect, the circuit breaker device is configured to require that a safety threshold be exceeded for a predetermined amount of time before switching the circuit breaker to the open position.

[0158] In a possible implementation form of the fifth aspect, the circuit breaker device is configured to use the first derivative or the second derivative of the signal from at least one sensor, as a supplement to or an alternative to the value of the signal itself, to determine whether the safety threshold has been exceeded.

[0159] In a possible implementation form of the fifth aspect, the sensor is arranged inside.

[0160] According to the sixth aspect, a method for operating a nuclear reactor that sustains a continuous nuclear fission chain reaction is provided. The nuclear reactor includes a closed container. Preferably, the nuclear reactor includes a closed and sealed leak - proof container that has an interior, and the interior of the container contains:

[0161] A nuclear reactor core;

[0162] At least a primary heat exchange circuit that includes a primary heat exchange medium pump for circulating a primary heat exchange medium in the primary heat exchange circuit;

[0163] At least one sensor configured to provide a signal indicative of the operating state of a nuclear reactor;

[0164] A circuit breaker device including a circuit breaker, the circuit breaker device being configured to connect at least one of the electrical and / or electronic components in the interior to a power source within the vessel and to disconnect at least one of the electrical and / or electronic components in the interior from the power source within the vessel; the circuit breaker device includes a circuit breaker having an open state and a closed state, and the circuit breaker device is connected to at least one sensor;

[0165] The method includes the circuit breaker device determining that a signal from the at least one sensor exceeds a safety threshold, preferably, the safety threshold being a safety threshold indicating that the molten salt nuclear reactor is operating in a scram mode, a critical component has failed, or another safety-critical threshold has been exceeded, and

[0166] Opening the circuit breaker when it has been determined that a signal from at least one sensor exceeds the safety threshold.

[0167] According to a seventh aspect, there is provided a nuclear reactor for maintaining a sustained nuclear fission chain reaction, the nuclear reactor including an enclosed vessel, preferably, the nuclear reactor including an enclosed and hermetically sealed vessel having an interior, the interior of the vessel containing:

[0168] A nuclear reactor core;

[0169] At least a primary heat exchange loop including a primary heat exchange medium pump for circulating a primary heat exchange medium in the primary heat exchange loop;

[0170] Piping for transporting an internal and an external heat exchange medium, the piping fluidly connecting an inlet and an outlet;

[0171] The inlet penetrates the exterior of the vessel and the outlet penetrates the exterior of the vessel;

[0172] A heat exchange device for exchanging heat between the primary heat exchange medium and the internal and external heat exchange medium;

[0173] At least one sensor configured to provide a signal indicative of the operating state of a nuclear reactor; and

[0174] A circuit breaker device, the circuit breaker device including a circuit breaker, the circuit breaker device being configured to connect at least one of the electrical and / or electronic components in the interior to a power source within the container and to disconnect at least one of the electrical and / or electronic components in the interior from the power source within the container; the circuit breaker device including a circuit breaker having an open state and a closed state, the circuit breaker device being connected to at least one sensor;

[0175] and the circuit breaker device being configured to open the circuit breaker when a signal from the at least one sensor exceeds a safety threshold, preferably, the safety threshold being a safety threshold indicating that the molten salt nuclear reactor is operating in a scram mode, a critical component has failed, or another safety critical threshold has been exceeded.

[0176] In a possible implementation form of the seventh aspect, the electrical and / or electronic components include one or more of the following:

[0177] - An electric motor for driving the primary heat exchange medium pump;

[0178] - An actuator of a normally closed valve located in the fluid supply pipeline of a turbine or a fluid-driven engine for driving the primary heat exchange medium pump;

[0179] - An actuator of a normally open salt valve, which allows the molten salt primary heat exchange medium to be discharged from the molten salt primary heat exchange loop when the normally open salt valve is opened.

[0180] In a possible implementation form of the seventh aspect, at least one sensor includes a sensor configured to sense the temperature of the primary heat exchange medium.

[0181] In a possible implementation form of the seventh aspect, the nuclear reactor is configured to end the nuclear reaction and enter a safe state when disconnecting at least one of the electrical and / or electronic components in the interior from the power source.

[0182] In a possible implementation form of the seventh aspect, the nuclear reactor is configured to start operating when the electrical and / or electronic components are connected to the power source, preferably, the nuclear reactor is configured to start operating when connecting the electrical and / or electronic components to the power source by switching the circuit breaker device from the open position to the closed position.

[0183] In a possible implementation form of the seventh aspect, the nuclear reactor is configured to end operation by disconnecting electrical components and / or electronic components from a power source. Preferably, the nuclear reactor is configured to end operation by switching a circuit breaker device from an open position to a closed position to disconnect the electrical components and / or electronic components from the power source.

[0184] In a possible implementation form of the seventh aspect, the circuit breaker device includes a circuit breaker and a controller, and the controller includes analog electronics and / or digital electronics, and the analog electronics and / or digital electronics are configured to operate the circuit breaker in an open mode or a closed mode.

[0185] In a possible implementation form of the seventh aspect, at least one sensor includes one or more of the following: a fuel salt temperature sensor at a position between the outlet of the primary heat exchanger and the fuel salt inlet of the nuclear reactor core; the fuel salt temperature at a position between the fuel salt outlet of the nuclear reactor core and the inlet of the primary heat exchanger; a fuel salt flow sensor. Preferably, the fuel salt flow is derived from the rotational speed of the primary pump.

[0186] In a possible implementation form of the seventh aspect, the circuit breaker device is configured to require that a safety threshold be exceeded for a predetermined amount of time before switching the circuit breaker to the open position.

[0187] In a possible implementation form of the seventh aspect, the circuit breaker device is configured to use the first derivative or the second derivative of a signal from at least one sensor, as a supplement to or an alternative to the value of the signal itself, to determine whether the safety threshold has been exceeded.

[0188] In a possible implementation form of the seventh aspect, the at least one sensor is arranged inside.

[0189] In a possible implementation form of the seventh aspect, the primary heat exchange medium pump is an open type. When the primary pump is not operating, the primary heat exchange medium pump opens to allow the primary heat exchange medium to pass through. Wherein, the primary heat exchange loop is fluidly connected to a primary exchange medium discharge tank, and wherein the nuclear reactor is configured to allow the primary heat exchange medium to be discharged by gravity into the primary exchange medium discharge tank when the primary pump stops, regardless of the reason for the primary pump to stop. Preferably, the nuclear reactor is configured to allow the primary heat exchange medium to be discharged by gravity into the primary exchange medium discharge tank when the primary pump stops, regardless of the reason for the primary pump to stop, and without the need for any flow control elements such as valves.

[0190] In a possible implementation form of the seventh aspect, the primary heat exchange medium pump is a centrifugal pump.

[0191] In a possible implementation of the seventh aspect, the primary heat exchange medium contains fissile material, and the primary heat exchange medium discharge tank is configured for passive decay heat removal.

[0192] According to an eighth aspect, there is provided a method of operating a nuclear reactor that sustains a continuous nuclear fission chain reaction, the nuclear reactor including a closed vessel, preferably a closed and hermetically sealed vessel having an interior, the interior of the vessel containing:

[0193] A nuclear reactor core;

[0194] At least a primary heat exchange loop including a primary heat exchange medium pump for circulating a primary heat exchange medium in the primary heat exchange loop; and

[0195] A pipe for transporting an internal and an external heat exchange medium, the pipe fluidly connecting an inlet and an outlet;

[0196] The inlet penetrates the exterior of the vessel, and the outlet penetrates the exterior of the vessel;

[0197] A heat exchange device for exchanging heat between the primary heat exchange medium and the internal and external heat exchange media;

[0198] At least one sensor configured to provide a signal indicative of the operating state of the nuclear reactor; and

[0199] A breaker circuit arrangement including a circuit breaker, the breaker circuit arrangement configured to connect at least one of the electrical and / or electronic components in the interior to a power source within the vessel and to disconnect at least one of the electrical and / or electronic components in the interior from the power source within the vessel, the breaker circuit arrangement including a circuit breaker having an open state and a closed state, the breaker circuit arrangement being connected to at least one sensor, the method including determining that a signal from the at least one sensor exceeds a safety threshold, preferably a safety threshold indicative of the nuclear reactor operating in a scrammed manner, a critical component having failed, or another safety critical threshold having been exceeded,

[0200] And opening the circuit breaker when it has been determined that a signal from the at least one sensor exceeds the safety threshold.

[0201] In a possible implementation form of the eighth aspect, when the circuit breaker is opened, the primary heat exchange medium is discharged from the primary heat exchange loop under the influence of gravity into a primary heat exchange medium discharge tank arranged below the primary exchange loop.

[0202] In a possible implementation form of the eighth aspect, when the circuit breaker is opened, the primary heat exchange pump stops, and wherein the primary heat exchange medium is allowed to be discharged from the primary heat exchange loop at least partially through the primary heat exchange pump under the influence of gravity.

[0203] In a possible implementation form of the eighth aspect, at least one of the electrical components and / or electronic components in the interior includes:

[0204] - an electric motor for driving the primary heat exchange medium pump;

[0205] - an actuator of a normally closed valve located in a fluid supply pipeline of a turbine or a fluid-driven engine for driving the primary heat exchange medium pump;

[0206] - an actuator of a normally open salt valve, which allows the molten salt primary heat exchange medium to be discharged from the molten salt primary heat exchange loop when the normally open salt valve is opened.

[0207] These aspects and other aspects will become apparent from the following embodiments. BRIEF DESCRIPTION OF THE DRAWINGS

[0208] In the following detailed part of the present disclosure, aspects, embodiments, and implementations will be explained in more detail with reference to the exemplary embodiments shown in the drawings, wherein:

[0209] Figure 1 is a schematic diagram of a first embodiment of a nuclear reactor connected to a heat consumption device;

[0210] Figure 2 is a schematic diagram of a second embodiment of a nuclear reactor connected to a heat consumption device;

[0211] Figure 3 is a schematic diagram of a third embodiment of a nuclear reactor connected to a heat consumption device;

[0212] Figure 4 is a schematic diagram of a fourth embodiment of a molten salt type nuclear reactor, Figure 5 is a schematic diagram of a fifth embodiment of a molten salt type nuclear reactor, Figure 6 is a schematic diagram of a sixth embodiment of a molten salt type nuclear reactor; and

[0213] Figure 7 is a schematic diagram of a seventh embodiment of a molten salt type nuclear reactor. DETAILED DESCRIPTION OF THE EMBODIMENTS

[0214] Figure 1 A first embodiment of a nuclear reactor 1 is shown. The nuclear reactor is arranged inside a hermetically sealed container 1, which is also referred to as a "reactor vessel". The hermetically sealed container 1 forms an airtight housing in which the components of the nuclear reactor are located. In an embodiment, the reactor vessel 1 is a metal outer shell, preferably, the reactor vessel 1 is a steel outer shell, such as an outer shell having a metal wall or a steel wall. In an embodiment, the reactor vessel 1 is provided with a wall container having two or more airtight layers, i.e., a double-walled container, a triple-walled container, etc., and the third barrier is, for example, particularly used for radiation protection ( Figure 1 not shown in the figure).

[0215] The interior of the reactor vessel 1 is optionally divided into a hot zone 30 (sometimes referred to as a "furnace") and a cold zone 35. The interior of the container 1 contains a nuclear reactor core 2 (preferably located in the hot zone 30) and a primary heat exchange circuit 3 for removing heat from the nuclear reactor core 2 (preferably also located in the hot zone 30) by circulating a primary heat exchange medium. Temperature-sensitive equipment, such as a power supply system and electronics, such as a controller 50, an uplink transmitter 33, is arranged in the cold zone 35 as much as possible.

[0216] The nuclear reactor is one or more of the following types of reactors (non-exhaustive list): pressurized water reactor, boiling water reactor, pressurized heavy water reactor, gas-cooled reactor, molten salt reactor, fast neutron reactor. The primary heat exchange medium is determined by the reactor type, and the primary heat exchange medium can be one or more of the following (non-exhaustive list): water, heavy water, helium, carbon dioxide, sodium, molten salt (fluoride salt or chloride salt), lead or lead-bismuth eutectic. Depending on the reactor type, the primary heat exchange medium not only removes heat from the reactor but also has additional functions, such as acting as a moderator or containing nuclear fuel.

[0217] During operation of a nuclear reactor, a continuous nuclear controlled chain reaction occurs in nuclear reactor core 2. Active and passive control of the continuous chain reaction involves adjusting the level of fission-induced neutrons in reactor core 2, and the manner of achieving this goal may depend on the type of reactor. In some types of reactors, adjusting the level of fission-induced neutrons in reactor core 2 involves moving control rods made of high neutron-absorbing material to absorb neutrons. One or more control rods (not shown) are inserted deeper into nuclear reactor core 2 to absorb more neutrons than the material or medium it displaces. This action results in fewer neutrons available to cause fission, thereby reducing the power output of the nuclear reactor. Conversely, removing one or more control rods will result in an increase in the fission event rate and an increase in the power output of the nuclear reactor. In other types of nuclear reactors, adjusting the level of fission-induced neutrons in reactor core 2 involves adjusting the temperature or amount of the moderator present in reactor core 2. In the case of a liquid moderator, reducing the temperature of the liquid moderator, producing a higher density of the liquid moderator, or increasing the level or amount of the liquid moderator in reactor core 2 to increase the level of fission-induced neutrons in reactor core 2 by causing a larger proportion of the fast neutrons released from fission to lose energy and become thermal neutrons, where thermal neutrons are more likely to cause fission or less likely to leak out of reactor core 2 than fast neutrons, and vice versa.

[0218] In Figure 1 an embodiment, the nuclear reactor is, for example, a molten salt reactor. In this embodiment, the primary heat exchange loop 3 includes a primary pump 4 for circulating a primary heat exchange medium in the primary heat exchange loop 3. The primary pump 4 is a circulation pump driven by a primary motor 5. Preferably, the primary motor is an electric drive motor provided with a motor drive for adjusting the speed of the electric motor 5. A heater (not shown) is provided for each heat exchange loop containing a heat exchange medium that is solid at normal room temperature or ambient temperature to allow the medium to be heated to the liquid phase so that the heated medium can be pumped. For example, the heater is an electric heater.

[0219] The primary heat exchange circuit 3 extends through the nuclear reactor core 2, and correspondingly, the nuclear reactor core 2 is provided with a primary heat exchange medium inlet 6 and a primary heat exchange medium outlet 7 for connecting the portion of the primary heat exchange circuit 3 that extends through the nuclear reactor core 2. The primary heat exchange circuit 3 passes through the primary heat exchanger 10 for exchanging heat with the internal and external heat exchange media, and passes through the primary heat exchange medium tank 17 that forms the lowest part of the primary heat exchange circuit 3. The primary pump 4 pumps the primary heat exchange medium from the primary exchange medium discharge tank 17. The primary pump 4 is driven by the primary electric motor 5, and the primary pump 4 is an open type, such as a centrifugal pump, which is opened to allow the primary heat exchange medium to pass through when the primary pump 4 is not operating (stopped). In this way, when the primary pump 4 stops, the primary heat exchange medium is discharged into the primary exchange medium discharge tank 17 due to gravity, and regardless of the reason for the stop of the primary pump 4, no flow control elements such as valves or pumps are required to ensure passive safety. The primary heat exchange medium discharge tank 17 is configured for passive decay heat removal. Preferably, the discharge tank includes passive cooling means for removing heat from the discharge tank 17, such as by conductive heat transfer through the bottom of the tank or by passive convective cooling according to a cooling medium that passes through the tank and is buoyancy-driven.

[0220] Inside the reactor vessel 1, there is arranged a pipe 23 for removing heat from the inside of the reactor vessel 1. The internal and external heat exchange media flow through the pipe 23. In an embodiment, the internal and external heat exchange media are molten nitrates, but they can also be another type of salt, or another type of suitable liquid, gas or vapor. The internal and external heat exchange media are pumped through the internal and external heat exchange medium pipe 23, which passes through the first heat exchanger 10 to remove the heat generated by the primary heat exchange medium and transfer this heat to the heat consuming device 100. The pipe 23 fluidly connects the inlet 38 and the outlet 39. Both the inlet 38 and the outlet 39 penetrate the wall of the vessel 1 for connection to an external heat consuming device 100.

[0221] The heat consumption device 100 is arranged outside the reactor vessel 1, and the heat consumption device 100 is fluidly connected to the reactor vessel 1 at the heat exchange medium inlet end 38 and the heat exchange outlet end 39, and the heat consumption device does not form part of the nuclear reactor. In this example, the heat consumption device 100 includes an external pipe 113, and the external pipe 113 together with the heat exchange pipe 23 forms an internal and external heat exchange liquid circuit passing through the interior of the external heat exchanger 90. The external pipe 113 is fluidly connected to both the inlet end 38 and the outlet end 39. An external pump 114 driven by an external electric motor 115 forces the internal and external heat exchange medium to circulate through the internal and external heat exchange circuits. The external controller 150 adjusts the speed of the external pump 114 to control the amount of heat absorbed by the internal and external heat exchange medium, thereby controlling the amount of heat transported out of the nuclear reactor. In this example, the external heat exchanger 90 is a boiler configured to exchange heat with the steam circuit 123, and the steam circuit is in turn connected to a steam turbine 130, and the steam turbine 130 drives an alternator 132 to generate electricity. However, it can be understood that the heat received by the heat consumption device 100 can be used for any other purpose, i.e., any process that requires heat, such as industrial processes, district heating, or desalination, and the electricity can be used for industrial purposes in addition to being supplied to the power grid, such as hydrogen production, hydrogen production for ammonia production, and metal refining and / or recycling.

[0222] The interior of the vessel 1 is provided with a plurality of sensors to provide data related to the operation of the nuclear reactor originating from the interior of the vessel.

[0223] At least the primary exchange circuit 3 is provided with a temperature sensor for sensing the temperature of the primary exchange medium. For example, the temperature sensor is in the form of a thermocouple ( Figure 1 (not shown in the figure). The temperature sensor generates a signal representing the sensed temperature. For the temperature as critical information, there will be two or more sensors to provide redundancy. In an embodiment, the temperature sensor is arranged in a thermocouple sheath (insert thermocouple sheath) or mounted on the tube surface (the tube surface of the tube transporting / accommodating the medium for which the temperature needs to be sensed).

[0224] In an embodiment, a first temperature sensor and a second temperature sensor (not shown) are arranged at the primary exchange circuit 3 (between the primary heat exchange medium outlet 7 and the primary exchange medium inlet of the secondary heat exchanger 20) for sensing the temperature of the primary exchange medium leaving the reactor core 2 for redundancy reasons. The second temperature sensor is arranged at the primary exchange circuit 3 and between the primary heat exchange medium outlet of the secondary heat exchanger 20 and the primary heat exchange medium inlet 6 for sensing the temperature of the primary exchange medium supplied to the reactor core 2.

[0225] Additional sensors disposed inside the vessel 1 can be one or more of the following: a radiation sensor, a pressure sensor, a vibration sensor, a sound sensor, a light sensor, a camera sensor, a flow sensor for sensing the liquid flow rate in any heat exchange loop or moderator loop (a flow meter (such as a turbine flow meter, a Venturi flow meter, an elbow flow meter, an ultrasonic flow meter) or a pump speed sensor), a pressure sensor for sensing the pressure in any heat exchange loop or moderator loop, a liquid component sensor for sensing the liquid components in any heat exchange loop or moderator loop (such as an electrochemical sensor, a laser-induced breakdown spectroscopy sensor, a Raman spectroscopy sensor), a gas component sensor, a gas leak detection sensor, a liquid leak detection sensor, a seismic sensor, an inclination sensor, a door switch sensor, an electromagnetic pulse sensor, and a geographical location sensor.

[0226] The controller 50 is disposed inside the reactor vessel 1, preferably as close as possible in the cold region 35. In an embodiment, the controller 50 is a distributed controller. The controller 50 does not receive any signals from outside the reactor vessel 1, but operates / depends on the data generated inside the reactor vessel 1, preferably only on the data generated inside the reactor vessel 1. The data generated inside the reactor vessel 1 at least partially originates from the sensors disposed inside the reactor vessel 1. The controller 50 receives signals from one or more sensors disposed inside the reactor vessel 1.

[0227] The controller 50 is configured to autonomously control the operation of the nuclear reactor depending on the data originating from inside the reactor vessel 1. Preferably, the controller 50 is configured to autonomously control the operation of the nuclear reactor only depending on the data originating from inside the reactor vessel 1. Preferably, the data originating from inside the vessel 1 includes at least one thermodynamic condition of the primary heat exchange medium.

[0228] The controller 50 is configured to control the power output of the nuclear reactor core 2 by adjusting the continuous nuclear fission chain reaction, thus by adjusting the level of fission-induced neutrons in the reactor core 2. The controller 50 is configured to control the power output of the nuclear reactor by adjusting the amount of heat generated by the nuclear reactor to the amount of heat removed from the nuclear reactor by the internal and external heat exchange media by controlling the nuclear chain reaction. The controller 50 is configured to control the speed of the primary pump 4 by controlling the power delivered to the primary electric motor 5, thereby controlling the nuclear chain reaction. In a molten salt reactor, assuming that the coolant temperature remains constant, adjusting the flow rate of the primary coolant indirectly affects the reactivity.

[0229] The controller 50 is configured to maintain the operating parameters of the nuclear reactor within one or more specified ranges, thereby allowing the heat generated by the nuclear reactor core 2 during at least normal operation of the nuclear reactor to be transferred through the internal and external heat exchange media in the primary heat exchanger 10, and allowing the nuclear fission chain reaction in the nuclear reactor to be regulated.

[0230] The controller 50 is configured to control the power output of the nuclear reactor core 2 as a function of the power absorbed by the internal and external heat exchange media in the heat exchange device. Preferably, the function is a function that ensures that the power output of the nuclear reactor core 2 is substantially equal to the power absorbed by the internal and external heat exchange media in the heat exchanger 10.

[0231] Preferably, the controller 50 is configured to adjust the speed of the primary pump 4 as a function of at least one thermodynamic condition of the primary heat exchange medium. Preferably, at least one thermodynamic condition is derived from one or more of the sensors disposed within the vessel 1, such as a temperature sensor configured to sense the temperature of the primary heat exchange medium. Preferably, the function includes one or more of a proportional part, an integral part, and a derivative part, and / or at least one controller 50 includes a model predictive controller.

[0232] At least one thermodynamic condition of the primary heat exchange medium may include the temperature of the primary heat exchange medium sensed by a temperature sensor disposed therein or its derivative.

[0233] The controller 50 is configured to maintain the temperature of the primary heat exchange medium at a specified temperature or within a specified temperature range as described below. Preferably, the controller 50 is configured to adjust the primary pump speed to maintain the fuel salt temperature at the fuel salt outlet 7 at approximately 700 °C. Preferably, adjusting the primary pump speed includes reducing the primary pump speed to increase the fuel salt temperature at the fuel salt outlet 7 and increasing the primary pump speed to decrease the fuel salt temperature at the fuel salt outlet 7.

[0234] A controller 50 includes one or more of analog electronics, digital electronics, software for processing electronic values, mechanical logic, hydraulic, and / or fluid logic. The controller 50 preferably does not include an electronic digital programmable computer and preferably, the controller 50 uses a redundant architecture. Even more preferably, the controller 50 uses different redundant architectures.

[0235] The controller 50 may optionally be coupled to a transmitter 33 configured to send an uplink signal to a remote receiver such as a remote server, thereby allowing remote monitoring of the operation of the nuclear reactor. However, as the name implies, the transmitter 33 can only transmit data and cannot receive data. Wherein, the controller is configured to send relevant data related to the operation of the nuclear reactor to the transmitter 33.

[0236] In an embodiment, the controller 50 uses "air gapping" to transfer data to a receiver outside the reactor vessel 1 to ensure that the controller 50 cannot receive any data or instructions and to prevent an attacker from attempting to spoof the data uplink to gain access to or control of the controller 50. Air gapping is a security measure that involves isolating the controller 50 and preventing the controller 50 from establishing external connections. Thus, the controller 50 is physically isolated and cannot make wireless or physical connections to other computers or network devices.

[0237] The heat sink device 100 (or human operator) can shut down the reactor by cutting off the power supply 53 to the electrical and electronic components in the reactor vessel 1, which mainly serves as an emergency shutdown. Subsequently, the primary heat exchange medium, secondary heat exchange medium, and other heat exchange media will automatically drain into their respective drain tanks.

[0238] Alternatively, the heat sink device 100 can shut down the reactor by stopping or reducing the flow rate of the internal and external heat exchange media through the pipes 23 to cause the reactor to stop generating heat. When the power demand from the heat sink device 100 drops below the decay heat generated during normal maximum operation (typically ~5% of full power), the reactor will shut down to handle the decay heat. Thus, if the heat sink device 100 drops to a consumption below the decay heat, the reactor will stop pumps 4, 14, 44 because the internal and external heat exchange media cannot remove sufficient heat and at least one of the salt (heat exchange medium) outlet temperatures will exceed its respective threshold. This is expected to be the most common way for the heat sink device 100 to shut down the reactor. The process will take several hours and can be initiated by the heat sink device 100, for example, to maintain the steam turbines 130, 132.

[0239] The primary loop 3 is not pressurized, i.e., it operates with the primary heat exchange medium at substantially atmospheric pressure.

[0240] When at least one reactor parameter or a combination of reactor parameters (e.g., in the form of thermodynamic conditions) among the reactor parameters is different from an acceptable operating value or range (the acceptable operating value or range is pre-stored and the controller 50 can access the acceptable operating value or range), the controller 50 will autonomously stop the reactor operation. In some embodiments, the controller 50 will automatically stop the reactor operation by allowing the liquid to be discharged under the influence of gravity into the discharge tank (17, 48). An example where one reactor parameter or a combination of reactor parameters among the reactor parameters is different from the acceptable operating value or range is that the flow rate in the primary loop 3 is above the acceptable value, or the fluid pressure in the primary loop or any other part of the system exceeds the acceptable value. Other examples where one reactor parameter or a combination of reactor parameters is different from the acceptable operating value are provided below.

[0241] Figure 2 A second embodiment of a nuclear reactor is shown. In this embodiment, for simplicity, structures and features that are the same as or similar to the corresponding structures and features previously described or shown herein are denoted by the same reference numerals as previously used. In this embodiment, the nuclear reactor includes a secondary coolant loop 13 disposed within the vessel 1. The secondary coolant loop passes through the primary heat exchanger 10 and exchanges heat with internal and external heat exchange media in the secondary heat exchanger 20. In this embodiment, the secondary heat exchange loop 13 includes a secondary pump 14 that circulates the secondary heat exchange medium in the secondary heat exchange loop 13. The secondary pump 14 is a circulation pump that is driven by a secondary motor 15. Preferably, the secondary motor is an electric motor. The secondary pump 14 is an open type, such as a centrifugal pump, and is opened to allow the primary heat exchange medium to pass through when the primary pump 14 is not operating (stopped). Thus, when the secondary pump 14 stops, the secondary heat exchange medium will be discharged into the secondary exchange medium discharge tank 27 due to gravity, regardless of the reason for the stop of the secondary pump 14, and no flow control elements such as valves or pumps are required to ensure passive safety. The secondary loop 23 is not pressurized, i.e., the secondary heat exchange medium operates at a second pressure that is substantially atmospheric.

[0242] In this embodiment, the controller 50 is configured to adjust the speed of the secondary pump 14, and its main purpose is to maintain the temperature of the secondary heat exchange medium within a predetermined bandwidth or near a predetermined set point. Preferably, the controller 50 is configured to adjust the speed of the secondary pump by adjusting the power supplied to the secondary pump motor 15 to maintain the fuel salt temperature at the fuel salt inlet 6 at approximately 600 °C. Preferably, adjusting the speed of the secondary pump includes: increasing the speed of the secondary pump to lower the temperature of the fuel salt at the fuel salt inlet 6, and decreasing the speed of the secondary pump to increase the temperature of the fuel salt at the fuel salt inlet 6.

[0243] Figure 3 The third embodiment of the nuclear reactor is shown. In this embodiment, for simplicity, structures and features that are the same as or similar to the corresponding structures and features previously described or shown in this document are denoted by the same reference numerals as those previously used. In this embodiment, a liquid moderator circuit 43 is included inside the nuclear reactor. The liquid moderator circuit 43 includes a moderator pump 44 that circulates the liquid moderator in the moderator circuit 43. The liquid moderator circuit 43 passes through the nuclear reactor core 2. Preferably, the liquid moderator circuit 43 passes through the nuclear reactor core 2 and through the liquid moderator heat exchanger 40. The liquid moderator heat exchanger 40 exchanges heat with internal and external cooling media, and the internal and external cooling media circulate through the liquid moderator heat exchanger and a cooler (not shown) arranged outside the container 1.

[0244] In this embodiment, preferably, at least one thermodynamic condition includes one or more of the following:

[0245] The temperature of the liquid moderator at a position between the liquid moderator outlet of the liquid moderator heat exchanger 40 and the liquid moderator inlet of the nuclear reactor core 2;

[0246] The temperature of the liquid moderator at a position between the liquid moderator outlet of the nuclear reactor core 2 and the liquid moderator inlet of the liquid moderator heat exchanger 40;

[0247] The liquid moderator flow rate, preferably, the liquid moderator flow rate is obtained according to the rotational speed of the three-stage pump 44.

[0248] The liquid moderator circuit 43 is not pressurized, that is, the liquid moderator operates at a second pressure that is substantially atmospheric.

[0249] Figure 4 The fourth embodiment is shown, in which the nuclear reactor is a molten salt nuclear reactor. In this embodiment, for simplicity, structures and features that are the same as or similar to the corresponding structures and features previously described or shown in this document are denoted by the same reference numerals as those previously used. The molten salt nuclear reactor is arranged inside a hermetically sealed container 1, which is also referred to as the "reactor vessel". The hermetically sealed container 1 forms an airtight housing, and the components of the molten salt nuclear reactor are located in the airtight housing. In the embodiment, the reactor vessel 1 is a metal outer shell. Preferably, the reactor vessel 1 is a steel outer shell, that is, an outer shell with a metal wall or a steel wall. In the embodiment, the reactor vessel 1 is provided with two airtight layers, that is, a double-walled container. As Figure 1 shown, the reactor vessel 1 has an inner wall 1' surrounded by an outer wall 1".

[0250] In an embodiment, the interior of the reactor vessel 1 is divided into a hot zone 30 (sometimes referred to as the furnace) and a cold zone 35. The interior of the vessel 1 includes a nuclear reactor core 2 (preferably located in the hot zone 30) and at least one salt loop 3, 13 (preferably located in the hot zone 30). In this embodiment, a liquid moderator loop 43 is housed within the vessel 1, and preferably, the liquid moderator loop 43 is housed within the interior of the vessel 1 and located in the hot zone.

[0251] The nuclear reactor will have at least a fuel salt loop 3 (primary loop), and optionally one or more coolant salt loops 13 (secondary and tertiary loops). Each salt loop 3, 13 includes pumps 4, 14 for circulating the molten salt in the associated salt loop 3, 13. Each salt loop 3, 13 contains a molten salt or molten salt mixture having suitable properties, such as fluoride salts or chloride salts. An example of a suitable salt for the molten salt loop is FLiBe (a mixture of lithium fluoride (LiF) and beryllium fluoride (BeF2)).

[0252] The fuel salt loop 3 extends through the nuclear reactor core 2, and correspondingly, the nuclear reactor core 2 is provided with a fuel salt inlet 6 and a fuel salt outlet 7 that connect to the portion of the fuel salt loop 3 that extends through the nuclear reactor core 2. The fuel salt includes fission components, and preferably, the fuel salt includes fission components rich in 7LiF-ThF4-UF4-UF3-PuF3 salts such as lithium heptafluoride, thorium tetrafluoride, uranium tetrafluoride, uranium trifluoride, and / or plutonium trifluoride. The fuel salt loop 3 passes through a first heat exchanger 10 for exchanging heat with the primary coolant salt and through a fuel salt drain tank 17 that forms the lowest portion of the fuel salt loop 3. The fuel salt pump 4 pumps the fuel salt up from the fuel salt drain tank 17. The fuel salt pump 4 is driven by a primary electric motor 5, and the fuel salt pump 4 is an open type, such as a centrifugal pump, which is opened to allow the fuel salt to pass through when the fuel salt pump 4 is not operating. Thus, when the fuel salt pump 4 stops, the fuel salt is drained by gravity into the fuel salt drain tank 17 without any flow control elements, such as valves or pumps.

[0253] One of the optional coolant salt loops is the primary coolant salt loop 13, which extends through the first heat exchanger 10 for exchanging heat with the fuel salt, through the second heat exchanger 20 for exchanging heat with the internal and external heat exchange media, and through the primary coolant salt drain tank 27 that forms the lowest part of the primary coolant salt loop 13. The primary coolant salt pump 14 pumps the primary coolant salt up from the primary coolant salt drain tank 27. The primary coolant salt pump 14 is driven by the secondary electric motor 15, and the primary coolant salt pump 14 is an open type, such as a centrifugal pump, which is opened to allow the primary coolant salt to pass through when the primary coolant salt pump 14 is not operating. Therefore, when the primary coolant salt pump 14 stops, the fuel salt is drained into the primary coolant salt drain tank 27 by gravity without any flow control elements such as valves or pumps. The primary coolant salt loop 13 is not pressurized, that is, the primary coolant salt operates at substantially atmospheric pressure.

[0254] The liquid moderator loop 43 extends through the nuclear reactor core 2, and correspondingly, the nuclear reactor core 2 is provided with a liquid moderator inlet 46 and a liquid moderator outlet 47 that connect to the part of the liquid moderator loop 43 extending through the nuclear reactor core 2. The liquid moderator loop 43 includes a moderator pump 44 for circulating the liquid moderator in the moderator loop 43. In an embodiment, the liquid moderator includes heavy water or molten hydroxides, preferably molten hydroxides of molten lithium-7 deuteroxide salt (7LiOD). The liquid moderator loop passes through the liquid third heat exchanger 40 to exchange heat between the liquid moderator and the liquid moderator cooling medium. The liquid moderator loop 43 extends through the liquid moderator drain tank 48 that forms the lowest part of the liquid loop 43. The tertiary pump 44 pumps the liquid moderator up from the liquid moderator drain tank 48. The tertiary pump 44 is a circulating pump driven by the tertiary electric motor 45, and the tertiary pump 44 is an open type, such as a centrifugal pump, which is opened to allow the liquid moderator salt to pass through when the tertiary pump 44 is not operating. Therefore, when the tertiary pump 44 stops, the liquid moderator enters the liquid moderator drain tank 48 by gravity without the need for any flow control elements such as valves or pumps. The tertiary pump is driven by the tertiary electric motor 45.

[0255] The liquid moderator coolant circulates in a liquid moderator coolant loop 63. The liquid moderator coolant loop 63 includes a liquid moderator coolant pump 64, a liquid moderator coolant drain tank 67, and a liquid moderator coolant cooler 60. The liquid moderator coolant pump 64 is driven by a four-stage electric motor 65 and is used to circulate the liquid moderator. Preferably, the liquid moderator coolant cooler 60 is arranged outside the reactor vessel 1. The liquid moderator coolant drain tank 67 forms the lowest part of the liquid moderator coolant loop 63. The liquid moderator coolant pump 64 is a circulation pump driven by a four-stage motor 65, and the liquid moderator coolant pump 64 is an open type, such as a centrifugal pump. When the liquid moderator coolant pump 64 is not operating, the liquid moderator coolant pump is opened to allow the liquid moderator to pass through. Therefore, when the liquid moderator coolant pump 64 stops, the liquid moderator coolant is discharged into the liquid moderator drain tank 48 due to gravity without any flow control elements such as valves or pumps.

[0256] The heat exchange medium pipe 23 for removing heat from inside the reactor vessel 1 is arranged inside the reactor vessel 1. The internal and external heat exchange media flow through the pipe 23 to exchange heat with the primary cooling salt in the second heat exchanger 20. In an embodiment, the internal and external heat exchange media are molten nitrate salts, but they can also be another type of salt, or another type of suitable liquid or gas, or vapor. The internal and external heat exchange media are pumped through the heat exchange medium pipe 23 and thus through the second heat exchanger 20 to remove the heat generated in the fuel salt and transfer the heat to the heat consuming device. The internal and external heat exchange medium pipe 23 fluidly connects the heat exchange medium inlet 38 and the heat exchange medium outlet 39. Both the heat exchange medium inlet 38 and the heat exchange medium outlet 39 lead to the outside of the vessel 1 for connection to an external heat consuming device, as described with reference to Figures 1 to 3 as described.

[0257] The fuel salt loop 3 is provided with temperature sensors 9 for sensing the temperature of the fuel salt leaving the reactor core 2, and the fuel salt loop 3 is also provided with a second temperature sensor 9' for redundancy. The signals of the sensors 9, 9' are transmitted to the controller 50. The fuel salt loop 3 may also be provided with a temperature sensor 59 for sensing the temperature of the fuel salt entering the reactor core 2. The signal of the sensor is transmitted to the controller 50.

[0258] The cooling salt circuit 13 is provided with a temperature sensor 22 for sensing the temperature of the cooling salt leaving the first heat exchanger 10. The cooling salt circuit 13 is also provided with a second temperature sensor 22' for redundancy. The signals of the sensors are transmitted to the controller 50. The cooling salt circuit 23 may also be provided with a temperature sensor 79 for sensing the temperature of the cooling salt entering the first heat exchanger 10. The signals of the sensors are transmitted to the controller 50.

[0259] Similarly, the moderator circuit is provided with a pair of temperature sensors 49, 49' for sensing the temperature of the liquid moderator leaving the reactor core 2, and the moderator circuit is provided with an additional temperature sensor 41 for sensing the temperature of the liquid moderator entering the reactor core 2. The signals of the sensors are transmitted to the controller 50.

[0260] The liquid moderator cooling circuit is provided with a temperature sensor 62 for sensing the temperature of the moderator cooling medium leaving the liquid moderator heat exchanger 40, and the liquid moderator cooling circuit is provided with a temperature sensor 61 for sensing the temperature of the liquid moderator cooling medium entering the liquid moderator heat exchanger 40.

[0261] The pipes 23 for the internal and external exchange media are provided with a pair of temperature sensors 89, 89' for sensing the temperature of the internal and external heat exchange media entering the pipes 23 through the inlet openings 38, and the pipes 23 are provided with a temperature sensor 99 for sensing the temperature of the internal and external heat exchange media leaving the pipes through the outlet 39.

[0262] The above temperature sensors can be implemented in the form of, for example, thermocouples or thermal switches. If the temperature sensor is a thermocouple, it generates a signal representing the sensed temperature. For temperatures that are critical information, there will be two or more sensors to provide redundancy. If the temperature sensor is a thermal switch, it generates a closed or open circuit, which can have a predetermined hard-wired temperature at which an open circuit is formed. For example, the open circuit can be used to trip a circuit breaker. For example, the thermal switch can use a bimetallic strip or differential thermal expansion to trigger with high reliability when the threshold temperature is reached.

[0263] In an embodiment, seismic sensors 57 are arranged inside 30, 35 of the reactor vessel 1. The signals of the seismic sensors 57 are transmitted to the controller 50 to allow the controller 50 to safely shut down the operation of the nuclear reactor when the sensor 57 senses a seismic event exceeding a predetermined level.

[0264] Figure 5 shows a fifth embodiment of a nuclear reactor. In this embodiment, for simplicity, structures and features that are the same as or similar to the corresponding structures and features previously described or shown herein are denoted by the same reference numerals as those previously used. This embodiment is substantially the same as Figure 4 the embodiment of [], except that the circuit breaker devices 19, 29, 69 have dedicated controllers 50', and the controller 50 is not used to control the circuit breaker devices 16, 29, 69.

[0265] Figure 6 shows a sixth embodiment of a nuclear reactor. In this embodiment, for simplicity, structures and features that are the same as or similar to the corresponding structures and features previously described or shown herein are denoted by the same reference numerals as those previously used. This embodiment is substantially the same as Figure 1 the embodiment of [], except that the primary pump 4 is driven by a turbine 25 or other fluid-driven motor, and the breaker circuit device 18 including the circuit breaker 19 is operatively connected to a normally closed valve 26. The normally closed valve 26 is arranged in a supply pipe that supplies fluid power (hydraulic or pneumatic power) to the turbine 25, and the normally closed valve 26 is moved to its open position (in the open position, the normally closed valve 26 allows fluid power to flow to the turbine 25) by an electric actuator (such as a solenoid) 27 and is moved to its closed position (in the closed position, the normally closed valve 26 does not allow fluid power to flow to the turbine 25) by, for example, an elastic element. The circuit breaker device 28 is connected to the controller 50, and the circuit breaker device 28 is configured to trip the circuit breaker 19 upon receiving a signal from the controller 50 to trip the circuit breaker. Thus, when the circuit breaker 29 trips (to its open position), the electric actuator is no longer energized, the normally closed valve 26 closes under the influence of the elastic element, the turbine 25 does not receive fluid power, and the primary pump 4 stops. This will allow the primary heat exchange medium to be discharged into the discharge tank 17, and the nuclear reaction in the core 2 stops.

[0266] Figure 7 shows a seventh embodiment of a nuclear reactor. In this embodiment, for simplicity, structures and features that are the same as or similar to the corresponding structures and features previously described or shown herein are denoted by the same reference numerals as those previously used. This embodiment is substantially the same as Figure 1The implementation manners are basically the same, except that the primary heat exchange circuit 3 is connected to the discharge pipe leading to the discharge tank 17 at a suitable (i.e., relatively low) position. A normally open valve 36 is arranged in the discharge pipe. The normally open valve 36 is moved to its closed position by an electric actuator (such as a solenoid) 37, and when the electric actuator 37 is not powered, the normally open valve 36 is moved to its open position (e.g., under the influence of an elastic element). The electric actuator 37 receives power through a circuit breaker device 18 including a circuit breaker 19. The circuit breaker device 18 is connected to the controller 50, and the circuit breaker device 18 is configured to trip the circuit breaker to its open position when receiving a signal from the controller 50 to trip the circuit breaker 19 to its open position. Therefore, when the circuit breaker device 18 receives a signal from the controller 50 to stop the operation of the nuclear reactor 1, the circuit breaker 19 trips to its open position, thereby cutting off the power supply to the electric actuator 37, which causes the normally open valve 36 to move to its open position, thereby allowing the primary heat exchange medium to be discharged from the primary exchange circuit 3 to the train tank 17, which causes the nuclear reaction in the nuclear reactor core 2 to stop.

[0267] In an embodiment, a radiation level sensor (not shown) is arranged inside the reactor vessel 1, and the radiation level sensor is used to generate a signal representing the radiation level inside the reactor vessel 1.

[0268] In an embodiment, the sensor is configured to emit a signal indicating the open position and / or closed position of a door (not shown) in the reactor vessel 1 to allow access to the interior (30, 35).

[0269] In an embodiment, one or more of the salt circuits 3, 13, the moderator circuit 43, and the heat exchange pipes 23 are provided with leakage sensors (not shown), and the leakage sensors are configured to emit leakage signals when a leakage occurs.

[0270] The controller 50 is arranged inside the reactor vessel 1. Preferably, the controller 50 is arranged inside the reactor vessel 1 and in the cold zone 35. In an embodiment, the controller 50 is a distributed controller, that is, it consists of several interconnected controllers that can be physically arranged at different positions. The controller 50 does not receive any data or signals from outside the reactor vessel 1. Instead, preferably, the controller 50 operates only based on / relies on the data generated inside the reactor vessel 1. The data generated inside the reactor vessel 1 at least partially originates from the sensors arranged inside the reactor vessel 1. The controller 50 receives signals from the sensors arranged inside the reactor vessel 1.

[0271] The controller 50 is configured to control the speed of the respective electric motors by sending signals to the drivers associated with the primary electric motor 5, the secondary electric motor 15, the tertiary electric motor 45, and the quaternary electric motor 65. The controller 50 is also configured to start and end the operation of the primary pump 5, the secondary pump 15, the tertiary pump 45, and the quaternary pump 65.

[0272] Additionally, the controller 50 may be configured to control the secondary electric motor 15, the tertiary electric motor 45, and the quaternary electric motor 65 to adjust the speeds of the secondary pump 14, the tertiary pump 44, and the tertiary pump 65. The controller 50 is also configured to start and end the operation of the primary pump 5, the secondary pump 15, the tertiary pump 45, and the quaternary pump 65.

[0273] The fuel salt circuit 3 supplies fuel salt to the reactor core 2 for driving and controlling the nuclear reaction. An optional moderator circuit supplies a liquid moderator to the reactor core 2 for controlling the nuclear reaction.

[0274] The controller 50 is configured to autonomously control the operation of the nuclear reactor depending on data originating from inside the vessel 1. Preferably, the controller 50 is configured to autonomously control the operation of the nuclear reactor depending only on data originating from inside the vessel 1. At least some of the data originating from inside the vessel 1 originates from one or more sensors arranged inside the vessel 1. Preferably, the data originating from inside the vessel 1 includes at least one thermodynamic condition of the primary heat exchange medium.

[0275] The at least one thermodynamic condition may include one or more of the following:

[0276] The fuel salt temperature or its derivative at a position between the outlet of the primary heat exchanger 10 and the fuel salt inlet 6 of the nuclear reactor core 2,

[0277] The fuel salt temperature or its derivative at a position between the fuel salt outlet 7 of the nuclear reactor core 2 and the inlet of the primary heat exchanger 10,

[0278] The fuel salt flow rate, preferably, the fuel salt flow rate is derived from the rotational speed of the primary pump 4,

[0279] The primary cooling salt temperature or its derivative at a position between the outlet of the secondary heat exchanger 20 and the primary cooling salt inlet of the primary heat exchanger 10,

[0280] The primary cooling salt temperature or its derivative at a position between the primary cooling salt outlet of the primary heat exchanger 10 and the inlet of the secondary heat exchanger 20,

[0281] The primary cooling salt flow rate, preferably, the primary cooling salt flow rate is derived from the rotational speed of the secondary pump 14,

[0282] The liquid moderator temperature at a position between the liquid moderator outlet of the liquid moderator heat exchanger 40 and the liquid moderator inlet of the nuclear reactor core 2;

[0283] The liquid moderator temperature at a position between the liquid moderator outlet of the nuclear reactor core 2 and the liquid moderator inlet of the liquid moderator heat exchanger 40;

[0284] The liquid moderator flow rate, preferably, the liquid moderator flow rate is obtained according to the rotational speed of the tertiary pump 44.

[0285] The controller 50 is configured to provide an output value that includes one or more of the following:

[0286] - The speed of the primary pump 4,

[0287] - The speed of the secondary pump 14,

[0288] - The speed of the tertiary pump 44,

[0289] - The speed of the quaternary pump 64,

[0290] - The speed of the blanket salt pump,

[0291] - The end of operation of the primary pump 4,

[0292] - The end of operation of the secondary pump 14,

[0293] - The end of operation of the tertiary pump 44,

[0294] - The end of operation of the quaternary pump 64,

[0295] - The end of operation of the blanket salt pump,

[0296] - The start of operation of the primary pump 4,

[0297] - The start of operation of the secondary pump 14,

[0298] - The start of operation of the tertiary pump 44,

[0299] - The start of operation of the quaternary pump 64,

[0300] - The start of operation of the blanket salt pump.

[0301] The controller 50 is configured to perform one or more of the following:

[0302] - Adjust the speed of the primary pump to maintain the fuel salt temperature at the fuel salt outlet 7 at approximately 700 °C. Preferably, adjusting the speed of the primary pump includes reducing the speed of the primary pump to increase the fuel salt temperature at the fuel salt outlet 7 and increasing the speed of the primary pump to decrease the fuel salt temperature at the fuel salt outlet 7.

[0303] - Adjust the speed of the tertiary pump to adjust the level of the liquid moderator in the core 2 of the nuclear reactor and thus adjust the reactivity to maintain the average temperature between the fuel salt inlet 6 and the fuel salt outlet 7 at approximately 650 °C. Preferably, adjusting the speed of the tertiary pump includes increasing the speed of the moderator pump to increase reactivity and decreasing the speed of the moderator pump to decrease reactivity.

[0304] - Adjust the speed of the secondary pump to maintain the temperature of the fuel salt at the fuel salt inlet 6 at approximately 600 °C. Preferably, adjusting the speed of the secondary pump includes increasing the speed of the secondary pump to decrease the temperature of the fuel salt at the fuel salt inlet 6 and decreasing the speed of the secondary pump to increase the temperature of the fuel salt at the fuel salt inlet 6.

[0305] - Adjust the speed of the moderator coolant pump to maintain the temperature of the liquid moderator at the liquid moderator outlet of the core 2 of the nuclear reactor at approximately 40 °C. Preferably, adjusting the speed of the moderator coolant pump includes increasing the speed of the tertiary pump to decrease the temperature of the liquid moderator at the liquid moderator outlet of the core 2 of the nuclear reactor and decreasing the speed of the tertiary pump to increase the temperature of the liquid moderator at the liquid moderator outlet of the core 2 of the nuclear reactor.

[0306] In an embodiment, the controller 50 is configured to control the level of the moderator in the core 2 of the nuclear reactor as a function of data originating from within the vessel 1. Thus, the controller adjusts the level (quantity) of the liquid moderator in the core 2 of the nuclear reactor. The level of the liquid moderator and the core of the reactor can be adjusted by adjusting the speed of the moderator pump 44, where the higher the speed, the higher the level of the moderator in the core of the reactor, and the lower the speed, the lower the level of the liquid moderator in the core of the nuclear reactor. This can be achieved, for example, by allowing the liquid moderator to passively drain back into the liquid moderator drain tank 48 and having a separate gas connection between the gas head volume of the liquid moderator tank in the core 2 and the gas head of the liquid moderator tank 48, and the gas pressure above the liquid level will be the same. Thus, the discharge flow rate of the liquid moderator in the core will be proportional to the height of the liquid moderator in the core 2 and concentrated on the flow rate of the tertiary pump 44. An adjusted flow restriction at or downstream of the liquid moderator outlet 47 allows for the desired relationship between the liquid moderator level and the flow rate or speed of the tertiary pump.

[0307] In an embodiment, the nuclear reactor includes breaker circuit devices 18, 28, 68 controlled by a controller 50 (a part of the controller 50 may be arranged as a part of the breaker circuit devices 18, 28, 68), and the breaker circuit devices 18, 28, 68 are configured to connect at least one of the electrical and / or electronic components 4, 14, 44 inside the vessel 1 to a power source 53 within the vessel 1 and to disconnect at least one of the electrical and / or electronic components 4, 14, 44 inside the vessel 1 from the power source 53 within the vessel 1. The breaker circuit devices 18, 28, 68 are connected to at least one sensor 9, 22, 41, 49, 59, 79, and the at least one sensor provides a signal representing the operation of the nuclear reactor. The breaker circuit devices 18, 28, 68 are configured to open one or more or all of the circuit breakers 19, 29, 69 when the signal from the sensors 9, 22, 41, 49, 59, 79 exceeds a safety threshold, preferably, the safety threshold is a safety threshold in the case where it indicates that the nuclear reactor is operating in a shutdown mode, a critical component has failed, or another safety-critical criterion has been exceeded.

[0308] In an embodiment, the breaker circuit devices 18, 28, 68 include circuit breakers 19, 29, 69 controlled by one of the controllers in the controller 50. The nuclear reactor is configured to end the nuclear reaction and enter a safe state when disconnecting at least one of the electrical and / or electronic components 5, 15, 45, 65 inside the vessel 1 from the power source 53. Thus, deactivating the power supply 53 will safely stop the operation of the nuclear reactor. As described above, the liquid circuits 3, 13, 43 inside are drained by gravity into their respective drain tanks 17, 27, and 48, and the nuclear reaction will stop. Preferably, the process of draining the liquid from the circuit is passive, that is, the process of draining the liquid from the circuit only occurs under the influence of gravity.

[0309] The controller 50 is configured to start the operation of the nuclear reactor by connecting the electrical and / or electronic components 5, 15, 45 to the power source 53 by switching the breaker circuit devices 18, 28, 68 from the open position to the closed position. The controller 50 is configured to end the operation of the nuclear reactor by disconnecting the electrical and / or electronic components 4, 14, 44, 65 from the power source 53 by switching the breaker circuit devices 18, 28, 68 from the closed position to the open position.

[0310] Each circuit breaker device 18, 28, 68 includes a circuit breaker 19, 29, 69 and one of at least one (partial) controller 50. Preferably, the controller 50 includes analog electronics and / or digital electronics, and the analog electronics and / or digital electronics are configured to operate the corresponding circuit breakers 19, 29, 69 in an open or closed manner. Preferably, the controller 50 does not include an electronic digital programmable computer.

[0311] The controller 50 is configured to, when at least one reactor parameter or a combination of reactor parameters (e.g., in the form of thermodynamic conditions) among the reactor parameters is different from the acceptable operating value or range, stop the reactor operation mainly and automatically by allowing the liquid to drain into the drain tank 17, 48 under the influence of gravity, for example, by opening the circuit breaker, thereby allowing the heat exchange liquid to drain into the corresponding drain tanks 17, 27, 48, 67 under the influence of gravity, and stop the reactor operation mainly and automatically. Examples of acceptable operating values are (non-exhaustive list):

[0312] · The door of the reactor vessel 1 is closed (open, otherwise the reactor shuts down)

[0313] · The leak detection sensor shows no leak (open, otherwise the reactor shuts down)

[0314] · The radiation detector is below the threshold (open, otherwise the reactor shuts down)

[0315] · The first derivative of the radiation detector is below the threshold (open, otherwise the reactor shuts down)

[0316] · The reactor vessel furnace is between 580 °C and 720 °C (open, otherwise the reactor shuts down)

[0317] · The fuel salt inlet temperature is between 580 °C and 720 °C (open, otherwise the reactor shuts down)

[0318] · The fuel salt inlet temperature is between 580 °C and 720 °C (open, otherwise the reactor shuts down)

[0319] · The first coolant salt inlet temperature is between 480 °C and 720 °C (open, otherwise the reactor shuts down)

[0320] · The first coolant salt inlet temperature is between 480 °C and 720 °C (open, otherwise the reactor shuts down)

[0321] · The second coolant salt inlet temperature is between 300 °C and 580 °C (open, otherwise the reactor shuts down)

[0322] · The second coolant salt inlet temperature is between 300 °C and 580 °C (open, otherwise the reactor shuts down)

[0323] · The inlet temperature of the covering salt is between 580 °C and 720 °C (open, otherwise the reactor shuts down). · The inlet temperature of the covering salt is between 580 °C and 720 °C (open, otherwise the reactor shuts down).

[0324] · The inlet temperature of the scrubber salt is between 580 °C and 720 °C (open, otherwise the reactor shuts down).

[0325] · The inlet temperature of the scrubber salt is between 580 °C and 720 °C (open, otherwise the reactor shuts down).

[0326] · The inlet temperature of the liquid moderator is between 5 °C and 90 °C (open, otherwise the reactor shuts down).

[0327] · The temperature of the liquid moderator is between 5 °C and 90 °C (open, otherwise the reactor shuts down).

[0328] · The inlet temperature of the liquid moderator coolant is between 5 °C and 90 °C (open, otherwise the reactor shuts down).

[0329] · The inlet temperature of the liquid moderator coolant is between 5 °C and 90 °C (open, otherwise the reactor shuts down).

[0330] · The speed of the primary pump 4 is lower than a predetermined threshold (open, otherwise the reactor shuts down),

[0331] · The flow rate of the primary heat exchange medium is lower than a predetermined threshold (open, otherwise the reactor shuts down),

[0332] · The pressure of the primary heat exchange medium is lower than a predetermined threshold (open, otherwise the reactor shuts down).

[0333] In an embodiment, the nuclear reactor is configured to end the nuclear reaction and enter a safe state when disconnecting at least one of the electrical components and / or electronic components 5, 15, 45 inside from the power source 53. In an embodiment, the nuclear reactor is configured to start operating when the electrical components and / or electronic components 5, 15, 45 are connected to the power source 53. Preferably, the nuclear reactor is configured to start operating when connecting the electrical components and / or electronic components to the power source by switching the circuit breakers 19, 29, 69 of the breaker circuit devices 18, 28, 68 from the open position to the closed position.

[0334] In an embodiment, the nuclear reactor is configured to end the operation by disconnecting at least one of the electrical components and / or electronic components 5, 15, 45 from the power source 53 by switching the circuit breakers 19, 29, 69 of the breaker circuit devices 18, 28, 68 from the open position to the closed position.

[0335] In an embodiment, the circuit breaker devices 18, 28, 68 are configured to require that a safety threshold be exceeded for a predetermined amount of time before switching the circuit breakers 19, 29, 69 to the open position, such that an instantaneous action outside the safety threshold for a few seconds will not trip the circuit breakers 19, 29, 69.

[0336] In an embodiment, the circuit breaker devices 18, 28, 68 are configured to use the first derivative or the second derivative of a signal from one of the sensors 9, 22, 41, 49, 59, 79, as a supplement to or an alternative for the value of the signal itself, to determine whether the safety threshold has been exceeded.

[0337] In an embodiment, the procedure for starting the nuclear reactor includes connecting the controller 50 to the power source 53. Accordingly, the controller 50 starts to electrically heat the molten salt to reach the lower temperature threshold limit of the salt, and starts the pumps 4, 14, 44 when the salt has reached a sufficient temperature. If restarted after shutdown, at this time the power source remains on, and when the salt cools down and becomes lower than the lower threshold limit over a long period of time (several hours or days), the heater will start heating again (assuming of course that the power source is still connected) to prevent the salt from freezing. After shutdown, at this time the power source is disconnected, and when the salt cools below the threshold limit, once the power source is turned on again, the controller 50 starts to heat the salt using the heater to reach the minimum temperature limit, as if this were the first time the nuclear reactor was turned on, ignoring the earlier shutdown, and the controller 50 only considers the predefined target. Preferably, the threshold is set such that the controller 50 is not allowed to initiate a restart in certain cases, such as when the power source of the reactor has been turned off and the salt has reached 900 °C and a mechanical thermal switch (a switch that does not require a power source) is triggered, such that the controller is not allowed to initiate a restart. After such an event occurs, the reactor cannot be restarted because a limit has been reached where a restart is considered unsafe. Similarly, in an embodiment, a thermal switch is provided to detect whether the salt has cooled below the melting point of the salt, as salt freezing may damage components. Another similar situation involves the detection of a leak by a leak detection sensor, which, once triggered, will not allow the reactor to start again. Preferably, the leak detection sensor is configured to operate without power or with a battery, or to be able to sense a leak even after the power has been turned off or on.

[0338] Preferably, the nuclear reactor has a negative fuel reactivity coefficient, a negative moderator reactivity coefficient (if present), and a negative blanket reactivity coefficient (if present) to ensure stable power operation of the reactor core. Preferably, the nuclear reactor has a passive decay heat removal system.

[0339] In an embodiment, the fuel salt includes a fissile component. Preferably, the fuel salt includes a fissile component rich in lithium heptafluoride, uranium tetrafluoride, and depleted uranium trifluoride, i.e., a (7LiF)-(UF4)-(UF3) salt.

[0340] In an embodiment, the nuclear reactor core 2 includes a blanket (not shown) containing a blanket salt. Preferably, the blanket is connected to a blanket salt loop. In an embodiment, the blanket salt is a molten salt containing a fertile component. Preferably, the blanket salt is a molten salt rich in lithium heptafluoride and / or thorium tetrafluoride, i.e., a (7LiF-ThF4) salt.

[0341] In an embodiment, the power sources for the sensors and electronics are located behind the breaker circuit devices 18, 28, 68 such that when the circuit breakers 19, 29, 69 are opened and cut off the power to all the electronic and electrical components behind the breaker rings 18, 28, 68, the sensors and electronics remain operational.

[0342] In an embodiment, the nuclear reactor operates according to an inherently safe process that directly provides passive safety components under specific fault conditions in all operating modes.

[0343] In an embodiment, the nuclear reactor does not require any active intervention or electrical / electronic feedback on the part of the operator to bring the reactor into a safe shutdown state.

[0344] In an embodiment, the nuclear reactor is inherently safe, and preferably, the nuclear reactor does not rely on active systems to ensure the safety of the reactor.

[0345] Various aspects and implementations have been described in connection with various embodiments. However, those skilled in the art, when practicing the claimed subject matter, can understand and realize other variations of the disclosed embodiments by studying the drawings, the disclosure, and the appended claims. In the claims, the word "comprising" does not exclude other elements or steps, and the indefinite article "a" or "an" does not exclude a plurality. A single processor, controller, or other unit may perform the functions of multiple items recited in the claims. Just because certain measures are recited in mutually different dependent claims does not mean that a combination of these measures cannot be advantageously utilized.

[0346] The reference signs used in the claims should not be construed as limiting the scope. Unless otherwise stated, the drawings should be read together with the description (e.g., cross-hatching, component arrangement, scale, degree, etc.) and are considered part of the entire written description of the disclosure.

Claims

1. A nuclear reactor for maintaining a continuous nuclear fission chain reaction, said nuclear reactor comprising a closed vessel (1), preferably, said nuclear reactor comprising a closed and leak - tight vessel (1), said vessel (1) having an interior (30, 35), and said interior (30, 35) of said vessel (1) containing: A nuclear reactor core (2); At least a primary heat - exchange loop (3), said primary heat - exchange loop comprising a primary heat - exchange medium pump (4) for circulating a primary heat - exchange medium in said primary heat - exchange loop (3); A pipe (23) for transporting internal and external heat - exchange media, said pipe (23) fluidly connecting an inlet (38) and an outlet (39); Said inlet (38) penetrating the exterior of said vessel (1), and said outlet (39) penetrating the exterior of said vessel (1); A heat - exchange device for exchanging heat between said primary heat - exchange medium and said internal and external heat - exchange media, and At least one controller (50) configured to autonomously control the operation of said nuclear reactor depending on data originating within said vessel (1), in particular, said at least one controller is configured to autonomously control the reactivity of said nuclear reactor depending on data originating within said vessel (1); At least some of the data originating within said vessel (1) originate from one or more sensors arranged within said vessel (1), and the data originating within said vessel (1) includes at least one thermodynamic condition of said primary heat - exchange medium.

2. The nuclear reactor according to claim 1, wherein The reactivity of said nuclear reactor is controlled using closed - loop control, wherein the sensed process variable is the thermodynamic condition of said primary heat - exchange medium sensed by a sensor within said vessel (1) and transmitted to said at least one controller (50) or the radiation level of said reactor core (2).

3. The nuclear reactor according to claim 1 or 2, wherein, Said at least one controller (50) is configured to maintain the operating parameters of said nuclear reactor within one or more specified ranges, thereby allowing the heat generated by said nuclear reactor core (2) during at least the normal operation of said nuclear reactor to be transferred through said internal and external heat - exchange media in said heat - exchange device, and / or allowing the regulation of the nuclear fission chain reaction in said nuclear reactor.

4. The nuclear reactor according to any one of claims 1 to 3, wherein, Said at least one controller (50) is configured to control the power output of said nuclear reactor core (2) by adjusting the continuous nuclear fission chain reaction, preferably, said at least one controller (50) is configured to control the power output of said nuclear reactor core by adjusting the level of fission - induced neutrons in said reactor core (2).

5. The nuclear reactor according to any one of claims 1 to 4, wherein, The at least one controller (50) is configured to control the power output of the nuclear reactor core (2) as a function of the power absorbed by the internal and external heat exchange media in the heat exchange device, preferably, the function is a function that ensures that the power output of the nuclear reactor core (2) is substantially equal to the power absorbed by the internal and external heat exchange media in the heat exchange device.

6. The nuclear reactor according to any one of claims 1 to 5, wherein, The at least one controller (50) is configured to maintain the temperature of the primary heat exchange medium at a specified temperature or within a specified temperature range.

7. The nuclear reactor according to any one of claims 1 to 6, wherein, The at least one controller (50) is configured to adjust the speed of the primary heat exchange pump (4), preferably, the at least one controller (50) is configured to adjust the speed of the primary heat exchange pump (4) as a function of at least one thermodynamic condition of the primary heat exchange medium, preferably, the at least one thermodynamic condition is derived from one or more of the sensors arranged in the vessel (1), preferably, the function includes one or more of a proportional part, an integral part, and a derivative part, and / or the at least one controller (50) includes a model predictive controller.

8. The nuclear reactor according to any one of claims 1 to 7, wherein, At least one thermodynamic condition of the primary heat exchange medium includes the temperature of the primary heat exchange medium sensed by the temperature sensors (9, 9') arranged therein or its derivative.

9. The nuclear reactor according to any one of claims 1 to 8, wherein, The at least one controller (50) includes one or more of analog electronics, digital electronics, software for processing electronic values, mechanical logic, hydraulic and / or fluid logic, preferably, the at least one controller uses a redundant architecture, and even more preferably, the at least one controller uses different redundant architectures.

10. The nuclear reactor according to any one of claims 1 to 9, the nuclear reactor includes breaker circuit means (18, 28, 68), the breaker circuit means is configured to connect at least one of the electrical and / or electronic components (5, 15, 45) in the interior to the power source (53) in the vessel (1) and to disconnect at least one of the electrical and / or electronic components (5, 15, 45) in the interior from the power source in the vessel, preferably, the breaker circuit means (18, 28, 68) includes a circuit breaker (19, 29, 69), the circuit breaker is controlled by one of the at least one controller (50), preferably, the nuclear reactor is configured to end the nuclear reaction and enter a safe state when disconnecting at least one of the electrical and / or electronic components (5, 15, 45) in the interior from the power source (53).

11. The nuclear reactor according to claim 10, wherein, The at least one controller (50) is configured to start the operation of the nuclear reactor by connecting the electrical and / or electronic components (5, 15, 45) to the power source (53) by switching the breaker circuit means (18, 28, 68) from the open position to the closed position.

12. The nuclear reactor according to claim 10 or 11, wherein The at least one controller (50) is configured to end the operation of the nuclear reactor by connecting the electrical and / or electronic components (5, 15, 45) to the power source (53) by switching the breaker circuit devices (18, 28, 68) from an open position to a closed position.

13. The nuclear reactor according to claim 10, 11 or 12, wherein The breaker circuit devices (18, 28, 68) include a circuit breaker (19, 29, 69) and one of the at least one controller (50). Preferably, the one of the at least one controller (50) includes analog and / or digital electronics configured to operate the circuit breaker (19, 29, 69) in an open or closed manner. Preferably, the one of the at least one controller (50) does not include an electronic digital programmable computer.

14. The nuclear reactor according to any one of claims 1 to 3, wherein, The nuclear reactor is a molten salt nuclear reactor, the primary heat exchange medium is a fuel salt containing fission material, the primary heat exchange medium circuit (3) is a fuel salt circuit (3), the primary heat exchange medium pump (4) is a fuel salt pump (4), the heat exchange device includes a primary heat exchanger (10), the primary heat exchange circuit (3) passes through the primary heat exchanger, and wherein, preferably, the at least one thermodynamic condition includes one or more of the following: The fuel salt temperature or its derivative at a position between the outlet of the primary heat exchanger (10) and the fuel salt inlet (6) of the nuclear reactor core (2); The fuel salt temperature or its derivative at a position between the fuel salt outlet (7) of the nuclear reactor core (2) and the inlet of the primary heat exchanger (10); The fuel salt flow rate, preferably, the fuel salt flow rate is derived from the rotational speed of the primary pump (4).

15. The nuclear reactor according to claim 14, wherein, The interior includes a primary cooling salt circuit (13) that passes through the primary heat exchanger (10) to exchange heat with the fuel salt, and preferably, the primary cooling salt circuit (13) passes through the primary heat exchanger (10) to exchange heat with the fuel salt and the primary cooling salt circuit (13) passes through a secondary heat exchanger (20) to exchange heat with the interior and exterior heat exchange media. The primary cooling salt circuit (13) includes a secondary pump (14) for circulating the primary cooling salt in the primary cooling salt circuit (13), and wherein, preferably, the at least one thermodynamic condition includes one or more of the following: The primary cooling salt temperature or its derivative at a position between the outlet of the secondary heat exchanger (20) and the primary cooling salt inlet of the primary heat exchanger (10); The primary cooling salt temperature or its derivative at a position between the primary cooling salt outlet of the primary heat exchanger (10) and the inlet of the secondary heat exchanger (20); The primary cooling salt flow rate, preferably, the primary cooling salt flow rate is derived from the rotational speed of the secondary pump (14).

16. The nuclear reactor according to any one of claims 1 to 15, wherein, The interior includes a moderator device (43, 44) for adjusting the moderation level in the nuclear reactor core (2), and wherein the at least one controller (50) is configured to control the moderation level in the nuclear reactor core (2) as a function of data originating within the vessel (1).

17. The nuclear reactor according to claim 14, 15 or 16, wherein, The interior includes a liquid moderator circuit (43) that includes a moderator pump (44) for circulating liquid moderator in the moderator circuit (43), the liquid moderator circuit (43) passing through the nuclear reactor core (2), and preferably, the liquid moderator circuit (43) passes through the nuclear reactor core (2) and through a liquid moderator heat exchanger (40). Wherein, preferably, the at least one thermodynamic condition includes one or more of the following: The liquid moderator temperature at a position between the liquid moderator outlet of the liquid moderator heat exchanger (40) and the liquid moderator inlet of the nuclear reactor core (2); The liquid moderator temperature at a position between the liquid moderator outlet of the nuclear reactor core (2) and the liquid moderator inlet of the liquid moderator heat exchanger (40); the liquid moderator flow rate, and preferably, the liquid moderator flow rate is derived from the rotational speed of a tertiary pump (44).

18. The nuclear reactor according to any one of claims 1 to 17, wherein, The at least one controller (50) is configured to provide an output value that includes one or more of the following: - The speed of the primary pump (4), - The speed of the secondary pump (14), - The speed of the tertiary pump (44), - The speed of the liquid moderator pump (64), - The speed of the overlying salt pump, - The end of operation of the primary pump (4), - The end of operation of the secondary pump (14), - The end of operation of the tertiary pump (44), - The end of operation of the liquid moderator pump (64), - The end of operation of the overlying salt pump, - The start of operation of the primary pump (4), - The start of operation of the secondary pump (14), - The start of operation of the tertiary pump (44), - The start of operation of the liquid moderator pump (64), - The start of operation of the overlying salt pump.

19. The nuclear reactor according to any one of claims 1 to 18, wherein, The at least one controller (50) includes one or more of analog electronics, digital electronics, software for processing electronic values, mechanical logic, hydraulic and / or fluid logic, and wherein, preferably, the at least one controller (50) does not include an electronic digital programmable computer.

20. The nuclear reactor according to any one of claims 16 to 19, wherein, The at least one controller (50) is configured to perform one or more of the following: - Adjust the primary pump speed to maintain the fuel salt temperature at the fuel salt outlet (7) at approximately 700 °C, and preferably, adjusting the primary pump speed includes reducing the primary pump speed to increase the fuel salt temperature at the fuel salt outlet (7), and increasing the primary pump speed to decrease the fuel salt temperature at the fuel salt outlet (7). - Adjust the speed of the liquid moderator pump to adjust the level of the liquid moderator in the nuclear reactor core (2) and thus adjust the reactivity to maintain the average temperature between the fuel salt inlet (6) and the fuel salt outlet (7) at approximately 650 °C. Preferably, adjusting the speed of the liquid moderator pump includes increasing the speed of the moderator pump to increase reactivity and decreasing the speed of the moderator pump to decrease reactivity. - Adjust the speed of the secondary pump to maintain the temperature of the fuel salt at the fuel salt inlet (6) at approximately 600 °C. Preferably, adjusting the speed of the secondary pump includes increasing the speed of the secondary pump to decrease the temperature of the fuel salt at the fuel salt inlet (6) and decreasing the speed of the secondary pump to increase the temperature of the fuel salt at the fuel salt inlet (6). - Adjust the speed of the moderator coolant pump to maintain the temperature of the liquid moderator at the liquid moderator outlet of the nuclear reactor core (2) at approximately 40 °C. Preferably, adjusting the speed of the moderator coolant pump includes increasing the speed of the liquid moderator pump to decrease the temperature of the liquid moderator at the liquid moderator outlet of the nuclear reactor core (2) and decreasing the speed of the liquid moderator pump to increase the temperature of the liquid moderator at the liquid moderator outlet of the nuclear reactor core (2).

21. The nuclear reactor according to any one of the preceding claims, wherein, The at least one controller (50) is configured to operate as a controller having a proportional part, an integral part, and / or a derivative part, and / or as a model predictive controller.

22. The nuclear reactor according to any one of the preceding claims, wherein, The heat exchange pump (4) is provided with a drive that receives a pump rotational speed signal from the at least one controller (50), or, for a nuclear reactor according to any one of claims 18 to 21, wherein the secondary pump (14), the tertiary pump (44), and / or the liquid moderator pump (64) are provided with a drive that receives a pump rotational speed signal from the at least one controller (50). Preferably, each drive is powered by electricity from a power source (53) within and each drive receives power via a circuit breaker (19, 29, 49).

23. A method of operating a nuclear reactor according to any one of claims 14 to 22, the method including determining the power output of the molten salt nuclear reactor by controlling the amount of power absorbed by the internal and external heat exchange media flowing through the heat exchange medium conduit (23). Preferably, the method includes determining the power output of the molten salt nuclear reactor by controlling the flow rate of the internal and external heat exchange media flowing through the conduit (23).

24. A method of operating a nuclear reactor that sustains a continuous nuclear fission chain reaction, the nuclear reactor including a closed vessel (1). Preferably, the nuclear reactor includes a closed and sealed leak - proof vessel (1) having an interior (30, 35), and the interior (30, 35) of the vessel (1) contains: a nuclear reactor core (2); At least a primary heat exchange circuit (3), said primary heat exchange circuit including a primary heat exchange medium pump (4), said primary heat exchange medium pump being configured to circulate a primary heat exchange medium in said primary heat exchange circuit (3); and A pipe (23), said pipe being used to transport internal and external heat exchange media, said pipe (23) fluidly connecting an inlet (38) and an outlet (39); Said inlet (38) penetrates the exterior of said container (1), and said outlet (39) penetrates the exterior of said container (1); A heat exchange device, said heat exchange device being configured to exchange heat between said primary heat exchange medium and said internal and external heat exchange media; Said method includes autonomously controlling the operation of said nuclear reactor depending on data originating within said container (1), preferably, said method includes autonomously controlling the operation of said nuclear reactor only depending on data originating within said container (1), at least some of the data originating within said container (1) originating from one or more sensors arranged within said container (1), preferably, the data originating within said container (1) includes at least one thermodynamic condition of said primary heat exchange medium.

25. A nuclear reactor for maintaining a sustained nuclear fission chain reaction, said nuclear reactor including an enclosed container (1), preferably, said nuclear reactor includes an enclosed and hermetically sealed container (1), said container (1) having an interior (30, 35), said interior (30, 35) of said container (1) containing: A nuclear reactor core (2); At least a primary heat exchange circuit (3), said primary heat exchange circuit including a primary heat exchange medium pump (4), said primary heat exchange medium pump being configured to circulate a primary heat exchange medium in said primary heat exchange circuit (3); A pipe (23), said pipe being used to transport internal and external heat exchange media, said pipe (23) fluidly connecting an inlet (38) and an outlet (39); Said inlet (38) penetrates the exterior of said container (1), and said outlet (39) penetrates the exterior of said container (1); A heat exchange device, said heat exchange device being configured to exchange heat between said primary heat exchange medium and said internal and external heat exchange media; At least one sensor (9, 22, 41, 49, 59, 79), said at least one sensor being configured to provide a signal indicative of the operating state of said nuclear reactor, and A circuit breaker device (18, 28, 68), the circuit breaker device including a circuit breaker (19, 29, 69), the circuit breaker device (18, 28, 60) being configured to connect at least one of the electrical and / or electronic components (5, 15, 45) in the interior to a power source (53) within the container (1) and to disconnect at least one of the electrical and / or electronic components (5, 15, 45) in the interior from the power source (53) within the container (1); the circuit breaker device (18, 29, 68) includes a circuit breaker (19, 29, 69) having an open state and a closed state, the circuit breaker device (18, 29, 69) being connected to at least one sensor (9), and the circuit breaker device (18, 29, 69) being configured to open the circuit breaker (19, 29, 69) when a signal from the at least one sensor (9) exceeds a safety threshold, preferably, the safety threshold being a safety threshold indicating that the molten salt nuclear reactor is operating in a scram mode, a critical component has failed, or another safety critical threshold has been exceeded.

26. The nuclear reactor according to claim 25, wherein, The electrical and / or electronic components include one or more of the following: - An electric motor (5) for driving the primary heat exchange medium pump (4); - An actuator (27) of a normally closed valve (26) located in a fluid supply pipe of a turbine (25) or a fluid drive engine for driving the primary heat exchange medium pump (4); - An actuator (37) of a normally open salt valve (36), which allows the molten salt primary heat exchange medium to be discharged from the molten salt primary heat exchange loop (3) when the normally open salt valve (36) is open.

27. The nuclear reactor according to claim 26 or 26, wherein, The at least one sensor (9, 22, 41, 49, 59, 79) includes sensors (9, 59) configured to sense the temperature of the primary heat exchange medium.

28. The nuclear reactor according to any one of claims 26 to 27, wherein, The nuclear reactor is configured to end the nuclear reaction and enter a safe state when disconnecting at least one of the electrical and / or electronic components (5, 15, 45) in the interior from the power source (53).

29. The nuclear reactor according to any one of claims 25 to 28, wherein The nuclear reactor is configured to start operating when the electrical and / or electronic components (5, 15, 45) are connected to the power source (53), preferably, the nuclear reactor is configured to start operating when connecting the electrical and / or electronic components (5, 15, 45) to the power source (53) by switching the circuit breaker device (18, 28, 68) from an open position to a closed position.

30. The nuclear reactor according to any one of claims 25 to 29, wherein, The nuclear reactor is configured to end operation by disconnecting the electrical and / or electronic components (5, 15, 45) from the power source (53), preferably, the nuclear reactor is configured to end operation by switching the breaker circuit devices (18, 28, 68) from an open position to a closed position to disconnect the electrical and / or electronic components (5, 15, 45) from the power source (53).

31. The nuclear reactor according to any one of claims 25 to 30, wherein, The breaker circuit devices (18, 28, 68) include circuit breakers (19, 29, 69) and a controller (50), the controller (50) includes analog electronics and / or digital electronics, and the analog electronics and / or digital electronics are configured to operate the circuit breakers (19, 29, 69) in an open or closed manner.

32. The nuclear reactor according to any one of claims 25 to 31, wherein, The at least one sensor includes one or more of the following: A fuel salt temperature sensor (9) at a position between the outlet of the primary heat exchanger (10) and the fuel salt inlet (6) of the nuclear reactor core (2); the fuel salt temperature at a position between the fuel salt outlet (7) of the nuclear reactor core (2) and the inlet of the primary heat exchanger (10); a fuel salt flow sensor, preferably, the fuel salt flow is derived from the rotational speed of the primary pump (4).

33. The nuclear reactor according to any one of claims 25 to 32, wherein, The breaker circuit devices (18, 28, 68) are configured to require that a safety threshold be exceeded for a predetermined amount of time before switching the circuit breaker (19, 29, 69) to the open position.

34. The nuclear reactor according to any one of claims 25 to 33, wherein, The breaker circuit devices (18, 28, 68) are configured to use the first derivative or second derivative of the signal from the at least one sensor (9, 22, 41, 49, 59, 79), as a supplement or alternative to the value of the signal itself, to determine whether the safety threshold has been exceeded.

35. The nuclear reactor according to any one of claims 25 to 34, wherein, The at least one sensor (9, 22, 41, 49, 59, 79) is arranged inside.

36. The nuclear reactor according to any one of claims 25 to 35, wherein, The primary heat exchange medium pump (4) is open, and when the primary pump (4) is not operating, the primary heat exchange medium pump opens to allow the primary heat exchange medium to pass through, wherein the primary heat exchange loop (3) is fluidly connected to the primary exchange medium discharge tank (17), and wherein the nuclear reactor is configured to allow the primary heat exchange medium to be discharged by gravity into the primary exchange medium discharge tank (17) when the primary pump (4) stops, regardless of the reason for the primary pump (4) to stop, preferably, the nuclear reactor is configured to allow the primary heat exchange medium to be discharged by gravity into the primary exchange medium discharge tank (17) when the primary pump (4) stops, regardless of the reason for the primary pump (4) to stop, and without the need for any flow control elements, such as valves.

37. The nuclear reactor according to claim 36, wherein, The primary heat exchange medium pump (4) is a centrifugal pump.

38. The nuclear reactor according to claim 36 or 37, wherein, The primary heat exchange medium contains fission material, and the primary heat exchange medium discharge tank (17) is configured for passive decay heat removal.

39. A method of operating a nuclear reactor that sustains a continuous nuclear fission chain reaction, the nuclear reactor comprising a closed vessel (1), preferably a closed and hermetically sealed vessel (1), the vessel (1) having an interior (30, 35), the interior (30, 35) of the vessel (1) containing: a nuclear reactor core (2); at least a primary heat exchange circuit (3), the primary heat exchange circuit including a primary heat exchange medium pump (4) for circulating a primary heat exchange medium in the primary heat exchange circuit (3); and a pipe (23) for transporting an internal and external heat exchange medium, the pipe (23) fluidly connecting an inlet (38) and an outlet (39); the inlet (38) penetrating the exterior of the vessel (1), and the outlet (39) penetrating the exterior of the vessel (1); a heat exchange device for exchanging heat between the primary heat exchange medium and the internal and external heat exchange medium; at least one sensor (9, 22, 41, 49, 59, 79) configured to provide a signal indicative of the operating state of the nuclear reactor; and a circuit breaker device (18, 28, 68), the circuit breaker device including a circuit breaker (19, 29, 69), the circuit breaker device (18, 28, 60) configured to connect at least one of the electrical and / or electronic components (5, 15, 45) in the interior to a power source (53) within the vessel (1) and to disconnect at least one of the electrical and / or electronic components (5, 15, 45) in the interior from the power source (53) within the vessel (1), the circuit breaker device (18, 29, 68) including a circuit breaker (19, 29, 69) having an open state and a closed state, the circuit breaker device (18, 29, 69) being connected to at least one sensor (9), the method comprising: determining that a signal from the at least one sensor (9) exceeds a safety threshold, preferably a safety threshold indicative of the nuclear reactor operating in a scrammed manner, a critical component having failed, or another safety-critical threshold having been exceeded, and opening the circuit breaker (19, 29, 69) when it has been determined that a signal from the at least one sensor (9, 22, 41, 49, 59, 79) exceeds the safety threshold.

40. The method according to claim 39, the method including allowing the primary heat exchange medium to drain under the influence of gravity from the primary heat exchange circuit (2) into a primary heat exchange medium drain tank (17) disposed below the primary exchange circuit when the circuit breaker (19, 29, 69) is opened.

41. The method according to claim 39 or 40, wherein, When the circuit breaker (19, 29, 69) is opened, the primary heat exchange pump (4) stops, and wherein the primary heat exchange medium is allowed to be discharged at least partially from the primary heat exchange circuit (2) through the primary heat exchange pump (4) under the influence of gravity.

42. The method according to claim 39, 40 or 41, wherein At least one of the electrical and / or electronic components (5, 15, 45) in the interior comprises: - an electric motor (5) for driving the primary heat exchange medium pump (4); - an actuator (27) of a normally closed valve (26) located in a fluid supply pipe of a turbine (25) or a fluid drive engine for driving the primary heat exchange medium pump (4); - an actuator (37) of a normally open salt valve (36), which allows the molten salt primary heat exchange medium to be discharged from the molten salt primary heat exchange circuit (3) when the normally open salt valve (36) is opened.

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