Sodium-cooled fast neutron proliferation reactor operation mode control method
By using the characteristic parameters of the effective reproduction factors of the reactor, the nuclear power level and the average sodium temperature of the core outlet, the operation mode of the sodium-cold fast neutron proliferation reactor is controlled, and the problems of unstable and difficult to control in the existing technology are solved, and scientific and reasonable operation mode control is achieved.
Patent Information
- Application Number
- CN202411713129.7
- Authority / Receiving Office
- CN · China
- Patent Type
- Applications(China)
- Current Assignee / Owner
- Filing Date
- 2024-11-27
- Publication Date
- 2025-03-18
AI Technical Summary
The prior art is difficult to effectively control the operating mode of sodium-cold fast neutron proliferation reactors, resulting in unstable operation and difficulty in achieving scientific and reasonable control.
The reactor operation mode is controlled through the characteristic parameters of the reactor effective proliferation factor Keff, nuclear power level and core outlet average sodium temperature, including power operation, start-up, hot shutdown, cold shutdown and material replacement shutdown.
The operation mode of sodium-cold fast neutron proliferation reactor is achieved, which is in line with the actual operation conditions, and the stability and adjustability of the reactor are improved.
Abstract
Description
Technical Field
[0001] The present invention relates to the technical field of sodium-cooled fast neutron breeder reactor operation mode control, and in particular to a sodium-cooled fast neutron breeder reactor operation mode control method, device, computer equipment and storage medium. Background Art
[0002] As the main type of reactor for the fourth generation of nuclear power, the sodium-cooled fast neutron breeder reactor is an indispensable part of the development of the nuclear power industry. Determining the operation mode control technology of the sodium-cooled fast neutron breeder reactor, which has a relatively small number of operation modes, clear distinction between operation modes, and involves fewer and distinct characteristic parameters, has important practical significance for the subsequent production and commissioning of large-scale million-kilowatt sodium-cooled fast neutron breeder reactors and the establishment of operation mode control standards. Therefore, it is necessary to study a sodium-cooled fast neutron breeder reactor operation mode control technology. Summary of the invention
[0003] The object of the present invention is to provide a method, device, computer equipment and storage device for controlling the operating mode of a sodium-cooled fast neutron breeder reactor, which controls the reactor operating mode by characteristic parameters such as the effective breeding factor Keff of the reactor, the nuclear power level and the average sodium temperature at the core outlet, so as to realize scientific and reasonable control of the operating mode of the sodium-cooled fast neutron breeder reactor.
[0004] In order to achieve the above-mentioned purpose, the present invention provides a method for controlling the operation mode of a sodium-cooled fast neutron breeder reactor, which controls the reactor operation mode through the reactor effective multiplication factor Keff, the nuclear power level and the average sodium temperature at the core outlet; the reactor operation mode includes power operation, startup, hot shutdown, cold shutdown and refueling shutdown.
[0005] The effective proliferation factor Keff of the reactor characterizes the self-sustaining chain fission reaction in the core; the nuclear power level directly characterizes the power level of the nuclear reactor and is also an adjustable and controllable parameter of the reactor operation; the average sodium temperature at the core outlet is a parameter that characterizes the core cooling condition and has different limit ranges with different reactor powers; the reactor operation mode can be scientifically and reasonably controlled through the effective proliferation factor Keff of the reactor, the nuclear power level and the average sodium temperature at the core outlet.
[0006] As one of the achievable approaches, nuclear power levels do not include decay heat.
[0007] As one of the feasible ways, when the effective value-added factor Keff of the reactor is ≥ 0.99 and the nuclear power level is ≥ 1% FP, the reactor is controlled to enter the power operation mode; FP is the rated power of the reactor.
[0008] As one of the feasible ways, when the effective value-added factor Keff of the reactor is ≥ 0.99 and the nuclear power level is < 1% FP, the reactor is controlled to enter the startup mode; FP is the rated power of the reactor.
[0009] As one of the feasible ways, when the reactor effective increment factor Keff is less than 0.99 and the average sodium temperature at the core outlet is greater than 250°C, the reactor is controlled to enter the thermal shutdown mode.
[0010] As one of the feasible ways, when the reactor effective increment factor Keff is less than 0.99, the average sodium temperature at the core outlet is 220℃≤≤250℃, the reactor plug tin-bismuth alloy is in a solidified state and the temperature is ≤90℃, the reactor is controlled to enter the cold shutdown mode.
[0011] As one of the feasible ways, when the reactor effective increment factor Keff is less than 0.98, the average sodium temperature at the core outlet is 220℃≤≤250℃, the reactor plug tin-bismuth alloy begins to melt or is in a molten state and the temperature is greater than 90℃, the reactor is controlled to enter the refueling shutdown mode.
[0012] As one achievable manner, the reactor can only be transferred to the startup operation mode via the hot shutdown operation mode or the cold shutdown operation mode.
[0013] In order to achieve the above object, the present invention further provides a method for solving the above problem. The present invention also provides an operation mode control device for a sodium-cooled fast neutron breeder reactor, comprising:
[0014] Characteristic parameter acquisition module, used to obtain the effective value-added factor Keff, nuclear power level and average sodium temperature at the core outlet of the reactor in real time and send them to the control module;
[0015] The operation mode control module is used to control the operation mode corresponding to the reactor according to the effective value-added factor Keff, the nuclear power level and the average sodium temperature at the core outlet;
[0016] Reactor operation modes include power operation, startup, hot shutdown, cold shutdown and refueling shutdown.
[0017] In order to achieve the above-mentioned purpose, the present invention also provides a computer device, including a memory and a processor, wherein the memory stores computer-readable instructions, and when the processor executes the computer-readable instructions, the steps of the above-mentioned sodium-cooled fast neutron breeder reactor operation mode control method are implemented.
[0018] In order to achieve the above-mentioned object, the present invention also provides a computer-readable storage medium, on which computer-readable instructions are stored. When the computer-readable instructions are executed, the steps of the above-mentioned sodium-cooled fast neutron breeder reactor operation mode control method are implemented.
[0019] Beneficial technical effects of the present invention:
[0020] The sodium-cooled fast neutron breeder reactor operation mode control method, device, computer equipment and storage medium of the present invention control the reactor operation mode through characteristic parameters such as reactor effective breeding factor Keff, nuclear power level and average sodium temperature at core outlet, and after debugging and cycle verification, it conforms to the actual operation of the sodium-cooled fast neutron breeder reactor, thus realizing scientific and reasonable control of the sodium-cooled fast neutron breeder reactor operation mode. DETAILED DESCRIPTION
[0021] Unless otherwise defined, all technical and scientific terms used herein have the same meaning as commonly understood by technicians in the technical field to which this application belongs; the terms used in the specification of the application are only for the purpose of describing specific embodiments and are not intended to limit this application; the terms "including" and "having" in the specification and claims of this application and any variations thereof are intended to cover non-exclusive inclusions.
[0022] Reference to "embodiments" herein means that a particular feature, structure, or characteristic described in conjunction with the embodiments may be included in at least one embodiment of the present application. The appearance of the phrase in various locations in the specification does not necessarily refer to the same embodiment, nor is it an independent or alternative embodiment that is mutually exclusive with other embodiments. It is explicitly and implicitly understood by those skilled in the art that the embodiments described herein may be combined with other embodiments.
[0023] The technical solution of the present invention is clearly and completely described below in conjunction with specific embodiments.
[0024] The invention provides a method for controlling the operation mode of a sodium-cooled fast neutron breeder reactor, which controls the operation mode of the reactor through the effective multiplication factor Keff of the reactor, the nuclear power level and the average sodium temperature at the core outlet; the reactor operation mode includes startup, power operation, hot shutdown, cold shutdown and shutdown for refueling.
[0025] The effective proliferation factor Keff of the reactor characterizes the self-sustaining chain fission reaction in the core; the nuclear power level directly characterizes the power level of the nuclear reactor and is also an adjustable and controllable parameter of the reactor operation; the average sodium temperature at the core outlet is a parameter that characterizes the core cooling condition and has different limit ranges with different reactor powers; the reactor operation mode can be scientifically and reasonably controlled through the effective proliferation factor Keff of the reactor, the nuclear power level and the average sodium temperature at the core outlet.
[0026] In this embodiment, as one of the achievable ways, the nuclear power level does not include decay heat.
[0027] In this embodiment, as one of the feasible ways, when the effective value-added factor Keff of the reactor is ≥0.99 and the nuclear power level is ≥1%FP, the reactor is controlled to enter the power operation mode; FP is the rated power of the reactor.
[0028] In this embodiment, as one of the achievable methods, when the reactor effective value-added factor Keff≥0.99 and the nuclear power level is <1%FP, the reactor is controlled to enter the startup mode; FP is the rated power of the reactor.
[0029] In this embodiment, as one of the feasible ways, when the effective increment factor Keff of the reactor is less than 0.99 and the average sodium temperature at the core outlet is greater than 250° C., the reactor is controlled to enter the hot shutdown mode.
[0030] In this embodiment, as one of the feasible ways, when the reactor effective increment factor Keff is less than 0.99, 220℃≤average sodium temperature at the core outlet≤250℃, and the reactor plug tin-bismuth alloy is in a solidified state and the temperature is ≤90℃, the reactor is controlled to enter the cold shutdown mode.
[0031] In this embodiment, as one of the feasible ways, when the reactor effective increment factor Keff is less than 0.98, 220℃≤average sodium temperature at the core outlet is less than 250℃, the reactor plug tin-bismuth alloy begins to melt or is in a molten state and the temperature is greater than 90℃, the reactor is controlled to enter the refueling shutdown mode.
[0032] In this embodiment, as one of the achievable ways, the reactor can only be transferred to the startup operation mode via the hot shutdown operation mode or the cold shutdown operation mode.
[0033] As an implementation of the above method, the present invention provides an embodiment of a sodium-cooled fast neutron breeder reactor operation mode control device. The device embodiment corresponds to the embodiment of the above sodium-cooled fast neutron breeder reactor operation mode control method, and the device can be specifically applied to various electronic devices.
[0034] The sodium-cooled fast neutron breeder reactor operation mode control device described in this embodiment includes:
[0035] Characteristic parameter acquisition module, used to obtain the effective value-added factor Keff, nuclear power level and average sodium temperature at the core outlet of the reactor in real time and send them to the control module;
[0036] The operation mode control module is used to control the operation mode corresponding to the reactor according to the effective value-added factor Keff, the nuclear power level and the average sodium temperature at the core outlet;
[0037] Reactor operation modes include power operation, startup, hot shutdown, cold shutdown and refueling shutdown.
[0038] As an implementation of the above method, the present invention provides an embodiment of a computer device, and the embodiment of the computer device corresponds to the embodiment of the above sodium-cooled fast neutron breeder reactor operation mode control method.
[0039] The computer device described in this embodiment includes a memory, a processor and a network interface that are interconnected and communicated through a system bus. It should be noted that the present invention only shows a computer device with a memory, a processor and a network interface, but it should be understood that it is not required to implement all the components shown, and more or fewer components can be implemented instead. Among them, those skilled in the art can understand that the computer device here is a device that can automatically perform numerical calculations and / or information processing according to pre-set or stored instructions, and its hardware includes but is not limited to a microprocessor, an application-specific integrated circuit, a programmable gate array, a digital processor, an embedded device, etc.
[0040] The computer device may be a computing device such as a desktop computer, a notebook, a PDA, a cloud server, etc. The computer device may interact with a user through a keyboard, a mouse, a remote controller, a touch pad, or a voice control device.
[0041] The memory includes at least one type of readable storage medium, and the readable storage medium includes flash memory, hard disk, multimedia card, card-type memory, random access memory, static random access memory, read-only memory, electrically erasable programmable read-only memory, programmable read-only memory, magnetic memory, disk, optical disk, etc. In some embodiments, the memory may be an internal storage unit of the computer device, such as a hard disk or memory of the computer device. In other embodiments, the memory may also be an external storage device of the computer device, such as a plug-in hard disk, smart memory card, secure digital card, flash memory card, etc. equipped on the computer device. Of course, the memory may also include both the internal storage unit of the computer device and its external storage device. In this embodiment, the memory is generally used to store the operating system and various application software installed on the computer device, such as the computer-readable instructions of the above-mentioned sodium-cooled fast neutron breeder reactor operation mode control method. In addition, the memory may also be used to temporarily store various types of data that have been output or are to be output.
[0042] In some embodiments, the processor may be a central processing unit, a controller, a microcontroller, a microprocessor, or other data processing chip. The processor is generally used to control the overall operation of the computer device. In this embodiment, the processor is used to run the computer-readable instructions stored in the memory or process data, such as running the computer-readable instructions of the above-mentioned sodium-cooled fast neutron breeder reactor operation mode control method.
[0043] The network interface may include a wireless network interface or a wired network interface, which is generally used to establish a communication connection between the computer device and other electronic devices.
[0044] As an implementation of the above method, the present invention provides an embodiment of a computer-readable storage medium, and the embodiment of the computer-readable storage medium corresponds to the embodiment of the above sodium-cooled fast neutron breeder reactor operation mode control method.
[0045] The computer-readable storage medium described in this embodiment stores computer-readable instructions, and the computer-readable instructions can be executed by at least one processor to enable the at least one processor to perform the steps of the sodium-cooled fast neutron breeder reactor operation mode control method as described above.
[0046] The selection basis of the effective proliferation factor Keff of the reactor is as follows: if the neutron production rate in the reactor is exactly equal to the neutron disappearance rate, the chain fission reaction in the reactor will continue at a constant rate, that is, the chain fission reaction process is in a steady state. At this time, the reactor is in a critical state, and the effective proliferation factor Keff of the reactor is 1; if the number of neutrons in the reactor continues to decay over time, the reactor is in a subcritical state, and the effective proliferation factor Keff of the reactor is less than 1; if the number of neutrons in the reactor continues to increase over time, the reactor is in a supercritical state. In the critical state, the effective proliferation factor Keff of the reactor is greater than 1; considering the influence of neutron leakage in the reactor and the envelope of the range of reactor operation modes, when the reactor is in the startup and power operation modes, the effective proliferation factor Keff of the reactor is ≥ 0.99; when the reactor is in the hot shutdown and cold shutdown operation modes, the number of neutrons in the reactor continues to decay, and the effective proliferation factor Keff of the reactor is less than 0.99; when the reactor is in the refueling shutdown operation mode, considering the negative reactivity introduced by the shutdown system, the effective proliferation factor Keff of the reactor is less than 0.98.
[0047] The basis for selecting the nuclear power level is: in the reactor startup operation mode, the reactor is in a just-critical state, a nuclear heating point appears, and the nuclear power level is <100% FP; in the reactor power operation mode, the fuel temperature shows a clear upward trend, and the nuclear power level is ≥100% FP.
[0048] The basis for selecting the average sodium temperature at the core outlet is as follows: when using metallic sodium as the coolant, there are clear requirements for its impurity content, among which the most representative impurity is oxygen. The impurity oxygen content in the sodium is required to be less than 10ppm, and the corresponding blocking temperature of 10ppm is about 190℃. Due to the complex structure inside the core, in order to prevent the precipitation of impurities in the sodium from blocking the coolant flow and causing local cold spots, a certain margin is taken into account and the average sodium temperature at the core outlet is taken to be no less than 220℃.
[0049] When the reactor is in the cold shutdown and refueling shutdown operation modes, the average sodium temperature at the core outlet is not higher than 250℃, mainly considering the following factors: ① Control the temperature difference between the sodium side and the water side of the steam generator water inlet when the reactor is started. When the average sodium temperature at the core outlet is higher than 250℃, the average sodium temperature at the core outlet will be too high, which will cause the risk of equipment damage; ② Maintaining a high average sodium temperature at the core outlet in the shutdown state has a high economic cost; ③ Under the refueling shutdown condition, the average sodium temperature at the core outlet needs to be controlled between (220 and 250)℃. When the average sodium temperature at the core outlet is higher than 250℃, the core components are easy to deform and difficult to grasp. When the reactor is in the power operation mode, the core temperature is higher than 250℃ due to nuclear heating. In the startup and power operation modes of the reactor, the average sodium temperature at the core outlet is not required and is limited by the regulations and technical specifications.
[0050] In the reactor power operation mode, the reactor is in a critical state, the passive rods and safety rods are at the top of the reactor, the regulating rods and compensating rods are in critical positions, the two loops of the reactor are operating simultaneously, and the reactor power is between (1 and 100)% FP; the accident residual heat removal system is operational; the main container overpressure protection system is operational; the two primary-loop main circulation pump auxiliary motors are on standby, and can maintain the main pump at 25% of the rated speed when the auxiliary motor needs to be started; the steam generator is in water or water / steam working conditions.
[0051] In the reactor startup operation mode, the reactor approaches or reaches the critical state, the two loops of the reactor operate simultaneously, and the reactor power is <1% FP; the accident residual heat removal system can be operated; the main container overpressure protection system can be operated; the two primary circuit main circulation pump auxiliary motors are standby, and can maintain the main pump at 25% of the rated speed when the auxiliary motor needs to be started; the steam generator can be shut down or operate in water conditions; the reactor can only be transferred to the startup operation mode via the hot shutdown operation mode or the cold shutdown operation mode.
[0052] In the reactor hot shutdown operation mode, the reactor effective value-added factor keff is less than 0.99, meeting the shutdown depth requirements, and the average sodium temperature at the core outlet is greater than 250°C; the accident residual heat removal system can be operated; the main container overpressure protection system can be operated; at least one primary-loop main circulation pump auxiliary motor is on standby, which can maintain the main pump at 25% of the rated speed when the auxiliary motor needs to be started; the steam generator can be out of operation or in water or water / steam conditions; when the steam generator is not cut off and the metal temperature of the turbine steam inlet area is higher than 300°C, the unit can be started from a hot state.
[0053] In the reactor cold shutdown operation mode, the reactor effective value-added factor keff is less than 0.99, meeting the shutdown depth requirement, and the average sodium temperature at the core outlet is between 220°C and 250°C; within 3 days of entering the reactor cold shutdown operation mode, at least 3 accident residual heat removal systems are required to be operational; 3 days after entering the reactor cold shutdown operation mode, at least 2 accident residual heat removal systems are required to be operational; the main container overpressure protection system is operational; at least one primary-loop main circulation pump auxiliary motor is on standby, which can maintain the main pump at 25% speed when the auxiliary motor needs to be started; the steam generator can be operated without being put into operation or in water conditions.
[0054] When the reactor is in the refueling shutdown operation mode, the reactor effective value-added factor keff is less than 0.98, meeting the shutdown depth requirements, and the average temperature at the core outlet is between 220°C and 250°C; at least two accident residual heat removal systems are operational; the main container overpressure protection system is operational; at least one primary-loop main circulation pump auxiliary motor is on standby, which can maintain the main pump at 25% speed when the auxiliary motor needs to be started; all control rod assemblies of the reactor have been disengaged from the control drive mechanism grippers, and the control drive mechanism and the moving guide tube have been lifted to the refueling terminal; the reactor tin-bismuth alloy begins to melt or is in a molten state, with a temperature greater than 90°C; various components in the reactor core can be replaced; the steam generator can be operated without being put into operation or in water conditions.
[0055] The sodium-cooled fast neutron breeder reactor operation mode control method, device, computer equipment and storage medium of this embodiment control the reactor operation mode through characteristic parameters of reactor effective breeding factor Keff, nuclear power level and average sodium temperature at core outlet, and after debugging and cycle verification, it conforms to the actual operation of the sodium-cooled fast neutron breeder reactor and realizes scientific and reasonable control of the sodium-cooled fast neutron breeder reactor operation mode.
[0056] The above-mentioned embodiments only express several implementation methods of the present invention, and the description thereof is relatively specific and detailed, but it cannot be understood as limiting the scope of the patent of the present invention. It should be pointed out that, for ordinary technicians in this field, several variations and improvements can be made without departing from the concept of the present invention, which all belong to the protection scope of the present invention. Therefore, the protection scope of the patent of the present invention shall be subject to the attached claims.
Claims
1. A method for controlling an operation mode of a sodium-cooled fast neutron breeder reactor, characterized in that: The reactor operation mode is controlled by the reactor effective value-added factor Keff, the nuclear power level and the average sodium temperature at the core outlet; the reactor operation modes include power operation, startup, hot shutdown, cold shutdown and refueling shutdown.
2. The sodium-cooled fast neutron breeder reactor operation mode control method according to claim 1, characterized in that: The nuclear power level does not include decay heat; the reactor can only be transferred to the startup operation mode via the hot shutdown operation mode or the cold shutdown operation mode.
3. The sodium-cooled fast neutron breeder reactor operation mode control method according to claim 2, characterized in that: When the reactor effective value-added factor Keff≥0.99 and the nuclear power level≥1%FP, the reactor is controlled to enter the power operation mode; FP is the rated power of the reactor.
4. The sodium-cooled fast neutron breeder reactor operation mode control method according to claim 2, characterized in that: When the reactor effective increment factor Keff≥0.99 and the nuclear power level is <1%FP, the reactor is controlled to enter the startup mode; FP is the rated power of the reactor.
5. The sodium-cooled fast neutron breeder reactor operation mode control method according to claim 2, characterized in that: When the reactor effective increment factor Keff is less than 0.99 and the average sodium temperature at the core outlet is greater than 250°C, the reactor is controlled to enter the thermal shutdown mode.
6. The method for controlling the operation mode of a sodium-cooled fast neutron breeder reactor according to claim 2, characterized in that: When the reactor effective increment factor Keff is less than 0.99, the average sodium temperature at the core outlet is 220°C≤250°C, the reactor plug tin-bismuth alloy is in a solidified state and the temperature is ≤90°C, the reactor is controlled to enter the cold shutdown mode.
7. The method for controlling the operation mode of a sodium-cooled fast neutron breeder reactor according to claim 2, characterized in that: When the reactor effective increment factor Keff is less than 0.98, the average sodium temperature at the core outlet is 220℃≤≤250℃, the reactor plug tin-bismuth alloy begins to melt or is in a molten state and the temperature is greater than 90℃, the reactor is controlled to enter the refueling shutdown mode.
8. A sodium-cooled fast neutron breeder reactor operation mode control device, characterized in that: include: Characteristic parameter acquisition module, used to obtain the effective value-added factor Keff, nuclear power level and average sodium temperature at the core outlet of the reactor in real time and send them to the control module; The operation mode control module is used to control the operation mode corresponding to the reactor according to the effective value-added factor Keff, the nuclear power level and the average sodium temperature at the core outlet; Reactor operation modes include power operation, startup, hot shutdown, cold shutdown and refueling shutdown.
9. A computer device comprising a memory and a processor, wherein the memory stores computer-readable instructions, characterized in that: When the processor executes the computer-readable instructions, the steps of the sodium-cooled fast neutron breeder reactor operation mode control method according to any one of claims 1 to 7 are implemented.
10. A computer-readable storage medium having computer-readable instructions stored thereon, characterized in that: When the computer-readable instructions are executed, the steps of the sodium-cooled fast neutron breeder reactor operation mode control method according to any one of claims 1 to 7 are implemented.