Experimental simulation method, device and experimental equipment for water inlet accident of high-temperature gas cooled reactor

Abstract

The invention provides an experimental simulation method and device for a water inlet accident of a high-temperature gas cooled reactor and experimental equipment. The method comprises the following steps: polyethylene balls with different masses are uniformly placed in a reactor core of experimental equipment for the water inlet accident of the high-temperature gas cooled reactor so as to simulate the water inlet accident of the experimental equipment, and the experimental equipment is in a subcritical state; transmitting high-frequency pulse neutrons to the reactor core of the experimental equipment, and monitoring the reactivity of the reactor core to obtain a reactivity result of the reactor core; and based on the reactivity result, verifying the critical safety of the water inlet accident of the experimental equipment in the subcritical state. Therefore, according to the scheme, the polyethylene balls are adopted to replace water, the equivalent water inflow can be controlled, the corrosion effect of the water on the graphite material in the high-temperature gas cooled reactor is avoided, and the operation convenience and repeatability of the experiment are enhanced.

Description

TECHNICAL FIELD

[0001] The present application relates to the technical field of nuclear engineering experiments, and in particular to a method and device for simulating a water ingress accident of a high-temperature gas-cooled reactor and an experimental apparatus. BACKGROUND

[0002] A water ingress accident is a unique accident of a high-temperature gas-cooled reactor that can have serious consequences. The primary loop pressure boundary of a high-temperature gas-cooled reactor is composed of a reactor pressure vessel, a hot gas duct shell, and a steam generator shell. High-temperature helium gas from the reactor core flows through the outside of the steam generator heat transfer tubes to heat the cooling water on the secondary side to generate high-temperature steam. The working pressure on the secondary side is much higher than that on the primary side. Therefore, when the steam generator heat transfer tube breaks, the water and steam in the secondary loop will enter the primary loop under high pressure and enter the reactor core along with the helium gas, thereby causing positive reactivity insertion and threatening the critical safety of the reactor. SUMMARY

[0003] The present application aims to at least partially solve one of the technical problems in the related art.

[0004] To this end, a first object of the present application is to provide a method for simulating a water ingress accident of a high-temperature gas-cooled reactor, which uses polyethylene balls instead of water, is conducive to controlling the equivalent water ingress amount, avoids the corrosion effect of water on the graphite material in the high-temperature gas-cooled reactor, and enhances the operation convenience and repeatability of the experiment.

[0005] A second object of the present application is to provide a device for simulating a water ingress accident of a high-temperature gas-cooled reactor.

[0006] A third object of the present application is to provide an experimental apparatus.

[0007] To achieve the above objects, a first aspect of the present application provides a method for simulating a water ingress accident of a high-temperature gas-cooled reactor, comprising: uniformly placing polyethylene balls of different masses in the core of an experimental apparatus for a water ingress accident of a high-temperature gas-cooled reactor to simulate a water ingress accident of the experimental apparatus, the experimental apparatus being in a subcritical state; emitting high-frequency pulse neutrons to the core of the experimental apparatus and monitoring the reactivity of the core to obtain reactivity results of the core; and verifying the critical safety of the experimental apparatus in the subcritical state in a water ingress accident based on the reactivity results.

[0008] To achieve the above object, the second aspect of the present application provides an experimental simulation device for a high temperature gas cooled reactor water ingress accident, comprising: a simulation module, configured to uniformly place polyethylene balls with different masses in a core of an experimental device for a high temperature gas cooled reactor water ingress accident to simulate a water ingress accident of the experimental device, the experimental device being in a subcritical state; a monitoring module, configured to emit high-frequency pulse neutrons to the core of the experimental device and monitor reactivity of the core to obtain a reactivity result of the core; and a verification module, configured to verify critical safety of the experimental device in the water ingress accident in the subcritical state based on the reactivity result.

[0009] To achieve the above object, the third aspect of the present application provides an experimental device, comprising: a core, a high-frequency pulse neutron source and a neutron counter; the core comprises fuel balls and graphite balls which are uniformly mixed in equal numbers; the high-frequency pulse neutron source is configured to emit high-frequency pulse neutrons to the core; and the neutron counter is configured to monitor a decay curve of neutron flux in the core.

[0010] The experimental simulation method, device and experimental device for a high temperature gas cooled reactor water ingress accident provided by the present application can verify critical safety of an experimental device in a water ingress accident in a subcritical state by uniformly placing polyethylene balls with different masses in a core of an experimental device for a high temperature gas cooled reactor water ingress accident, emitting high-frequency pulse neutrons to the core of the experimental device, monitoring reactivity of the core to obtain a reactivity result of the core, and verifying critical safety of the experimental device in the water ingress accident in the subcritical state based on the reactivity result. Thus, the present application uses polyethylene balls instead of water, which is conducive to controlling equivalent water ingress and avoids corrosion of water on graphite materials in the high temperature gas cooled reactor, thereby enhancing operation convenience and repeatability of the experiment.

[0011] Additional aspects and advantages of the present application will be made apparent by the following description and the accompanying drawings. BRIEF DESCRIPTION OF DRAWINGS

[0012] The above and / or additional aspects and advantages of the present application will become apparent and be readily appreciated from the following description, including the accompanying drawings.

[0013] Figure 1 A flowchart of an experimental simulation method for a high temperature gas cooled reactor water ingress accident provided by an embodiment of the present application;

[0014] Figure 2 A schematic diagram of an experimental device provided by an embodiment of the present application;

[0015] Figure 3 A flowchart of another experimental simulation method for a high temperature gas cooled reactor water ingress accident provided by an embodiment of the present application;

[0016] Figure 4 FIG. 1 is a structural schematic diagram of an experimental device for a high-temperature gas-cooled reactor water ingress accident according to an embodiment of the present application;

[0017] Figure 5 FIG. 1 is a structural schematic diagram of an experimental device for a high-temperature gas-cooled reactor water ingress accident according to an embodiment of the present application; DETAILED DESCRIPTION

[0018] Embodiments of the present application are described in detail below with reference to the accompanying drawings, in which the same or similar components have the same or similar designations and functions throughout various figures and / or embodiments, and examples of embodiments of the present application are illustrated in the drawings. Embodiments described below with reference to the drawings are illustrative, and are intended to explain the present application, and are not understood as limiting the present application.

[0019] An experimental simulation method and device for a high-temperature gas-cooled reactor water ingress accident according to an embodiment of the present application are described below with reference to the accompanying drawings.

[0020] Figure 1 FIG. 2 is a flowchart of an experimental simulation method for a high-temperature gas-cooled reactor water ingress accident according to an embodiment of the present application, as shown in FIG. 2, the experimental simulation method for a high-temperature gas-cooled reactor water ingress accident according to an embodiment of the present application includes but is not limited to the following steps: Figure 1

[0021] S101, uniformly placing polyethylene balls of different masses in the core of the experimental device for a high-temperature gas-cooled reactor water ingress accident to simulate a water ingress accident of the experimental device, the experimental device being in a subcritical state.

[0022] It should be noted that the execution subject of the experimental simulation method for a high-temperature gas-cooled reactor water ingress accident provided by the present application is the experimental device for a high-temperature gas-cooled reactor water ingress accident. The core of the experimental device is a cylinder, and the periphery is surrounded by a reflection layer made of graphite bricks. As shown in the schematic diagram of the experimental device in FIG. 1. Figure 2

[0023] It can be understood that polyethylene material has similar molecular structure and physical properties as water, and the mass of polyethylene can be converted into the equivalent water ingress amount in the core by molecular weight to simulate the water ingress accident of the experimental device for a high-temperature gas-cooled reactor water ingress accident.

[0024] In some embodiments, the core of the experimental device for a high-temperature gas-cooled reactor water ingress accident contains the same number of uniformly mixed fuel balls and graphite balls, so that the experimental device is in a subcritical state. By mixing polyethylene balls into the core, the situation of water and steam entering the core when a water ingress accident occurs can be simulated.

[0025] ​​In some embodiments, the effect of different water inflow on the reactivity of the core can be simulated by changing the mass of the mixed polyethylene balls. Optionally, the polyethylene balls can be mixed into the core of the experimental device in order of mass from small to large. Optionally, the polyethylene balls can also be mixed into the core of the experimental device in order of mass from large to small.

[0026] S102, emitting high-frequency pulsed neutrons to the core of the experimental device and monitoring the reactivity of the core to obtain a reactivity result of the core.

[0027] In some embodiments, a high-frequency pulsed neutron source can be installed above the core of the experimental device, and the reactivity of the core can be monitored by emitting high-frequency pulsed neutrons from the high-frequency pulsed neutron source to the core of the experimental device and by monitoring the attenuation of the neutrons, thereby obtaining the reactivity result.

[0028] In some embodiments, the reactivity of the core can be calculated based on the attenuation constant of the high-frequency pulsed neutrons, and the reactivity of the core can be obtained as the reactivity result. Optionally, a counter can be used to count the neutron flux of the core within a set time period, and the attenuation constant of the high-frequency pulsed neutrons can be obtained based on the neutron flux, so that the reactivity of the core can be calculated based on the attenuation constant to obtain the reactivity result.

[0029] S103, verifying the critical safety of the experimental device in the water inflow accident under the subcritical state based on the reactivity result.

[0030] In some embodiments, the reactivity of the core can be calculated based on the reactivity result, and the critical safety of the experimental device in the water inflow accident under the subcritical state can be verified based on the reactivity indicator parameter. Optionally, the effective multiplication factor can be calculated based on the reactivity result as the reactivity indicator parameter of the core.

[0031] In some embodiments, the critical safety of the experimental device in the water inflow accident under the subcritical state can be verified based on the set threshold value and the calculated effective multiplication factor. For example, a set value corresponding to the effective multiplication factor can be set, and the effective multiplication factor and the set value can be compared to verify the critical safety of the experimental device in the water inflow accident under the subcritical state according to the comparison result.

[0032] In some embodiments, if the effective multiplication factor is less than the set value, it can be determined that the water inflow accident of the experimental device under the subcritical state is safe; if the effective multiplication factor is equal to the set value, it can be determined that the water inflow accident of the experimental device under the subcritical state is in the critical safety.

[0033] In the experimental simulation method for the water ingress accident of the high temperature gas cooled reactor provided in the embodiments of the present application, different masses of polyethylene balls are uniformly placed in the core of the experimental device for the water ingress accident of the high temperature gas cooled reactor, and high-frequency pulse neutrons are emitted to the core of the experimental device to monitor the reactivity of the core to obtain the reactivity result of the core, so that the critical safety of the experimental device in the subcritical state under the water ingress accident can be verified based on the reactivity result. Thus, the polyethylene balls are used to replace water in the present scheme, which is conducive to controlling the equivalent water ingress amount and avoiding the corrosion effect of water on the graphite material in the high temperature gas cooled reactor, and the operation convenience and repeatability of the experiment are enhanced.

[0034] Figure 3 The flowchart of the experimental simulation method for the water ingress accident of the high temperature gas cooled reactor provided in the embodiments of the present application is shown in FIG. 1. Figure 3 The experimental simulation method for the water ingress accident of the high temperature gas cooled reactor provided in the embodiments of the present application includes but is not limited to the following steps:

[0035] S301, different masses of polyethylene balls are uniformly placed in the core of the experimental device for the water ingress accident of the high temperature gas cooled reactor to simulate the water ingress accident of the experimental device.

[0036] In the embodiments of the present application, the implementation mode of step S301 can be implemented by any one of the embodiments of the present application, which is not limited herein and will not be repeated.

[0037] S302, high-frequency pulse neutrons are emitted to the core of the experimental device, and the reactivity of the core is monitored to obtain the reactivity result of the core.

[0038] In some embodiments, after the high-frequency pulse neutrons are emitted to the core of the experimental device, the decay curve of the neutron flux in the core can be monitored based on the neutron counter to determine the decay constant of the neutron flux.

[0039] It can be understood that the neutron flux decays exponentially over time. The neutron counter can monitor the neutron flux in the core within a set time period, and determine the decay curve of the neutron flux within the set time period according to the change of the neutron flux and the decay law, so that the decay constant of the neutron flux can be determined according to the decay curve.

[0040] Alternatively, the formula corresponding to the exponential decay law of the neutron flux over time is as follows:

[0041] n(t)∝e- αt (1)

[0042] Where n is the neutron flux, t is the set time period, and a is the decay constant.

[0043] That is, by monitoring the neutron flux of the core within a set time length and substituting into formula (1), the decay constant of the neutron flux can be calculated.

[0044] Further, the reactivity of the core can be calculated based on the decay constant. That is, the reactivity of the core can be determined as the reactivity result based on the decay constant.

[0045] Optionally, the formula for calculating the reactivity of the core is as follows:

[0046]

[0047] Wherein, ρ represents the reactivity, λ is the decay constant of the delayed neutron precursor, and Λ is the prompt neutron generation time, which is usually a constant.

[0048] That is, the reactivity of the core is calculated by substituting the decay constant of the neutron flux into formula (2) as the reactivity result.

[0049] S303, based on the reactivity result, determine the effective multiplication factor of the core under the influence of polyethylene balls of different masses.

[0050] In some embodiments, the effective multiplication factor of the core under the influence of polyethylene balls of different masses can be determined according to the correlation between the reactivity result and the effective multiplication factor. Wherein, the correlation between the reactivity result and the effective multiplication factor corresponds to the formula as follows:

[0051]

[0052] Wherein, k eff represents the effective multiplication factor, and β represents the delayed neutron fraction.

[0053] Optionally, the delayed neutron fraction can be calculated based on the physical model of nuclear fission and decay by calculating the decay chain of fission fragments and neutron emission probability.

[0054] Further, the effective multiplication factor can be calculated according to formula (3), and the calculation formula is as follows:

[0055]

[0056] S304, based on the effective multiplication factor and the set value, verify the critical safety of the experimental equipment in the subcritical state under the water injection accident.

[0057] In some embodiments, the critical safety of the experimental device in the water- in-accident of the subcritical state can be verified by comparing the size of the effective multiplication factor and the set value. Alternatively, if the effective multiplication factor is less than the set value, it can be determined that the safety state of the experimental device is safe; if the effective multiplication factor is equal to the set value, it can be determined that the safety state of the experimental device is critical safety.

[0058] That is, in response to the effective multiplication factor being less than the set value, the mass of the polyethylene ball is increased, and the step of determining the effective multiplication factor is repeatedly executed until the effective multiplication factor is equal to the set value, to determine that the experimental device is in a node of critical safety.

[0059] Exemplarily, the flow of the experimental simulation of the water-in-accident of the high-temperature gas-cooled reactor is explained with the set value being 1:

[0060] Step 1. The graphite balls and fuel balls are filled in the experimental device core in disorder and uniformly, and the reactor is kept in a subcritical state.

[0061] Step 2. The polyethylene balls with a mass of m are uniformly loaded in the core.

[0062] Step 3. The decay law of the neutron flux with time is observed by the neutron counter, the neutron counting decay curve is drawn, and the decay constant a is obtained.

[0063] Step 4. The reactivity p is obtained by substituting the decay constant a into formula (2), and then the effective multiplication factor k of the core under the influence of the polyethylene balls with a mass of m is obtained by substituting p into formula (4). eff .

[0064] Step 5. If k eff is less than 1, steps 2-4 are repeated to obtain the effective multiplication factor k eff of the core under different masses of the polyethylene balls, until k eff = 1, to verify the critical safety of the core.

[0065] In some embodiments, after determining that the experimental device is in a node of critical safety, the water-in-accident of the high-temperature gas-cooled reactor can also be warned according to the node of critical safety of the experimental device.

[0066] In some embodiments, the target mass of the polyethylene ball corresponding to the node of critical safety of the experimental device is determined, and the critical water-in-amount of the experimental device is determined based on the target mass. Alternatively, the target mass critical water-in-amount can be determined by the molecular weight, so that the water-in-accident of the high-temperature gas-cooled reactor can be warned based on the critical water-in-amount.

[0067] That is, when the water-in-amount of the water-in-accident of the high-temperature gas-cooled reactor reaches the critical water-in-amount, the water-in-accident of the high-temperature gas-cooled reactor is warned.

[0068] In the experimental simulation method for the water ingress accident of the high-temperature gas-cooled reactor provided by the embodiments, the decay curve of the neutron flux in the reactor core is monitored to determine the reactivity of the reactor core according to the decay curve, which has a good effect of simulating the reactivity change in the water ingress accident of the high-temperature gas-cooled reactor. By using the high-frequency pulsed neutron source to emit pulsed neutrons, the measurement of the neutron flux decay can be completed in a very short time, without waiting for the delayed neutrons to completely decay, thereby significantly shortening the experimental period.

[0069] Figure 4 FIG. 1 is a structural schematic diagram of an experimental device for a water ingress accident of a high-temperature gas-cooled reactor according to an embodiment of the present application, as shown in the figure, the experimental device 400 for the water ingress accident of the high-temperature gas-cooled reactor according to the embodiment includes a reactor core 401, a high-frequency pulsed neutron source 402, and a neutron counter 403. Figure 4

[0070] In some embodiments, the reactor core 401 of the experimental device 400 includes fuel balls and graphite balls mixed uniformly in the same number, so that the experimental device 400 is in a subcritical state. By mixing polyethylene balls into the reactor core 401, the water ingress accident of the experimental device 400 can be simulated.

[0071] In some embodiments, the high-frequency pulsed neutron source 402 of the experimental device 400 is used to emit high-frequency pulsed neutrons to the reactor core 401. The neutron counter 403 is used to monitor the decay curve of the neutron flux in the reactor core 401, so that the decay constant of the neutron flux can be determined based on the decay curve, and the reactivity of the reactor core can be determined as a reactivity result based on the decay constant.

[0072] Further, the effective multiplication factor of the reactor core under the influence of different masses of polyethylene balls can be determined according to the reactivity result, so that the critical safety of the subcritical state of the experimental device under the water ingress accident can be verified according to the effective multiplication factor.

[0073] In some embodiments, in response to the effective multiplication factor being less than a set value, the mass of the polyethylene balls is increased, and the step of determining the effective multiplication factor is repeatedly performed until the effective multiplication factor is equal to the set value, to determine the node at which the experimental device is in the critical safety.

[0074] In some embodiments, the neutron counter 403 can be installed in a counter channel of the experimental device 400, where the counter channel is a counter channel surrounding the middle part of the experimental device.

[0075] ​The experimental equipment for the high temperature gas cooled reactor water ingress accident provided in the embodiments of the present application includes: the polyethylene balls of different masses are mixed into the core of the experimental equipment, the high frequency pulse neutron source emits high frequency pulse neutrons to the core, and the reactivity of the core is monitored by the neutron counter to obtain the reactivity result of the core, so that the critical safety of the experimental equipment in the subcritical state under the water ingress accident can be verified based on the reactivity result. Thus, the polyethylene balls are used to replace water, which is beneficial to control the equivalent water ingress amount and avoids the corrosion effect of water on the graphite material in the high temperature gas cooled reactor, and the operation convenience and repeatability of the experiment are enhanced.

[0076] Corresponding to the experimental simulation method for the high temperature gas cooled reactor water ingress accident provided in the above several embodiments, one embodiment of the present application further provides an experimental simulation device for the high temperature gas cooled reactor water ingress accident. Since the experimental simulation device for the high temperature gas cooled reactor water ingress accident provided in the embodiments of the present application corresponds to the experimental simulation method for the high temperature gas cooled reactor water ingress accident provided in the above several embodiments, the implementation manners of the experimental simulation method for the high temperature gas cooled reactor water ingress accident described above are also applicable to the experimental simulation device for the high temperature gas cooled reactor water ingress accident provided in the embodiments of the present application, which will not be described in detail in the following embodiments.

[0077] In order to implement the above embodiments, the present application further provides an experimental simulation device for the high temperature gas cooled reactor water ingress accident.

[0078] Figure 5 A structural schematic diagram of an experimental simulation device for the high temperature gas cooled reactor water ingress accident provided in the embodiments of the present application.

[0079] As shown in Figure 5 , the experimental simulation device for the high temperature gas cooled reactor water ingress accident 500 includes:

[0080] The simulation module 501 is configured to uniformly place the polyethylene balls of different masses in the core of the experimental equipment for the high temperature gas cooled reactor water ingress accident to simulate the water ingress accident of the experimental equipment, and the experimental equipment is in a subcritical state.

[0081] The monitoring module 502 is configured to emit high frequency pulse neutrons to the core of the experimental equipment and monitor the reactivity of the core to obtain the reactivity result of the core.

[0082] The verification module 503 is configured to verify the critical safety of the experimental equipment in the subcritical state under the water ingress accident based on the reactivity result.

[0083] In one possible implementation manner of the embodiments of the present application, the verification module 503 is further configured to: determine the effective multiplication factor of the core under the influence of the polyethylene balls of different masses based on the reactivity result; and verify the critical safety of the experimental equipment in the subcritical state under the water ingress accident based on the effective multiplication factor and a set value.

[0084] In a possible implementation of the embodiment of the application, the verification module 503 is further configured to: in response to the effective multiplication factor being less than the set value, increase the mass of the polyethylene ball, and repeatedly perform the step of determining the effective multiplication factor until the effective multiplication factor is equal to the set value, to determine that the experimental device is at a critical safety node.

[0085] In a possible implementation of the embodiment of the application, the verification module 503 is further configured to: determine a target mass of the polyethylene ball corresponding to the node at which the experimental device is at a critical safety, and determine a critical water inflow of the experimental device based on the target mass; and based on the critical water inflow, perform early warning on the high-temperature gas cooled reactor water inflow accident.

[0086] In a possible implementation of the embodiment of the application, the monitoring module 502 is further configured to: based on the neutron counter, monitor a decay curve of the neutron flux in the core to determine a decay constant of the neutron flux; and based on the decay constant, determine the reactivity of the core as the reactivity result.

[0087] The experimental simulation device for the high-temperature gas cooled reactor water inflow accident provided in the embodiment of the application can monitor the reactivity of the core by placing polyethylene balls of different masses uniformly in the core of the experimental device for the high-temperature gas cooled reactor water inflow accident and emitting high-frequency pulse neutrons to the core of the experimental device, to obtain the reactivity result of the core, so that the critical safety of the experimental device in the subcritical state in the water inflow accident can be verified based on the reactivity result. Thus, the polyethylene balls are used to replace water, which is conducive to controlling the equivalent water inflow and avoids the corrosion effect of water on the graphite material in the high-temperature gas cooled reactor, and the operation convenience and repeatability of the experiment are enhanced.

[0088] It should be noted that the foregoing description of the embodiment of the method for simulating the high-temperature gas cooled reactor water inflow accident is also applicable to the experimental simulation device for the high-temperature gas cooled reactor water inflow accident, which will not be described here again.

[0089] In the foregoing embodiment description, the description of the terms "one embodiment", "some embodiments”, "an example”, "a specific example”, or "some examples” means that the specific features, structures, materials or characteristics described in connection with the embodiment or example are included in at least one embodiment or example of the application. In the description, the illustrative description of the above terms does not necessarily refer to the same embodiment or example. Moreover, the specific features, structures, materials or characteristics described can be combined in any appropriate manner in any one or more embodiments or examples. In addition, the person skilled in the art can combine and combine the different embodiments or examples described in the description and the features of the different embodiments or examples without contradiction.

[0090] Moreover, the terms "first", "second", "third", etc. are used herein only to describe different steps or categories of steps in a claim for patent purposes, and are not to be construed as indicating or implying relative importance of one step to another or a quantity of steps. Thus, features defined with "first", "second" or "third" can explicitly or implicitly include at least one of the features. In the description of the present application, the meaning of "plurality" is at least two, for example, two, three, etc., unless otherwise explicitly and specifically limited.

[0091] Any process or method descriptions or blocks in flow charts herein and elsewhere can be understood as representing modules, segments, or portions of code which include one or more executable instructions for implementing specific logical functions or steps in the process, and alternate implementations are possible. In some embodiments, the processes or methods described in flow charts herein and elsewhere can be tailored by reordering steps and / or adding or omitting one or more of the described steps, and the order of the steps can or can not be specifically mentioned or critical. One of ordinary skill in the art will recognize that the steps in the processes or methods described herein and elsewhere can be implemented by processor-executable code stored on a computer-readable medium, which can be incorporated in software, applied to the process or method, or otherwise used to implement the process or method.

[0092] Logic and / or steps represented in flow charts herein and elsewhere, for example, can be embodied in computer-readable instructions, statements, or in the form of one or more modules, segments, or portions of code that implement specified logical functions. Such computer-readable instructions can be loaded onto a computer, in one or more ways, and executed thereby. Such computer-readable instructions can include, for example, instructions in a computer-readable form, computer-executable instructions, or instructions that modify the operation of or management of the computer or components thereof, or a combination thereof. For purposes of this application, a "computer-readable medium" can be any apparatus that can contain, store, communicate, propagate, or transport the program for use by or in connection with the instruction execution system, apparatus, or device. Computer readable medium can typically be a computer- readable storage medium. The computer-readable storage medium can include, but is not limited to, an electronic, magnetic, optical, electromagnetic, infrared, or semiconductor system, apparatus, or device, or a propagation medium. The computer-readable storage medium can also include, without limitation, an electrical connection based on one or more wires, a portable computer diskette, a hard disk, a random access memory (RAM), a read-only memory (ROM), an erasable programmable read-only memory (EPROM or Flash memory), an optical fiber, and a portable compact disc read-only memory (CD-ROM). The computer-readable medium can also include, without limitation, a paper or other suitable medium upon which the program is printed, as the program can be electronically captured, via, for instance, optical scanning of the paper or other medium, then compiled, interpreted, or otherwise processed in a suitable manner, if necessary, and then stored in a computer memory.

[0093] It should be understood that parts of the present application can be realized in hardware, software, firmware, or a combination thereof. In the above embodiments, multiple steps or methods can be realized as software or firmware stored in a memory and executed by a suitable instruction execution system. As such, if realized in hardware, as in another embodiment, any of the following technologies or a combination thereof known in the art can be used: discrete logic circuitry having logic gates for implementing logic functions on data signals, application specific integrated circuits having appropriate combinational logic gates, programmable gate arrays (PGA), field programmable gate arrays (FPGA), etc.

[0094] Those skilled in the art of the present technology can understand that all or part of the steps carried out by the above-mentioned embodiments can be completed by a program instructing the relevant hardware, and the program can be stored in a computer readable storage medium. When the program is executed, it includes one of the steps of the method embodiments or a combination thereof.

[0095] In addition, each functional unit in each embodiment of the present application can be integrated into one processing module, or each unit can exist physically, or two or more units can be integrated into one module. The above-mentioned integrated module can be realized in the form of hardware or in the form of a software function module. The integrated module, if realized in the form of a software function module and sold or used as an independent product, can also be stored in a computer readable storage medium.

[0096] The above-mentioned storage medium can be a read-only memory, a magnetic disk or an optical disk, etc. Although the embodiments of the present application have been shown and described above, it should be understood that the above-mentioned embodiments are exemplary and cannot be understood as limiting the present application, and those skilled in the art can make changes, modifications, replacements and variations to the above-mentioned embodiments within the scope of the present application.

Claims

1. A method of experimental simulation of a loss of coolant accident for a high-temperature gas-cooled reactor, characterized in that, The method comprises: placing polyethylene balls of different masses uniformly in a core of an experimental device of a high temperature gas cooled reactor in order to simulate a loss of coolant accident of the experimental device, the experimental device being in a subcritical state; emitting high-frequency pulsed neutrons to the core of the experimental device and monitoring reactivity of the core to obtain a reactivity result of the core; verifying critical safety of the experimental device in the loss of coolant accident in the subcritical state based on the reactivity result.

2. The method of claim 1, wherein, The verifying critical safety of the experimental device in the loss of coolant accident in the subcritical state based on the reactivity result comprises: determining an effective multiplication factor of the core under the influence of the polyethylene balls of different masses based on the reactivity result; verifying critical safety of the experimental device in the loss of coolant accident in the subcritical state based on the effective multiplication factor and a set value.

3. The method of claim 2, wherein, The verifying critical safety of the experimental device in the loss of coolant accident in the subcritical state based on the effective multiplication factor and a set value comprises: in response to the effective multiplication factor being less than the set value, increasing the mass of the polyethylene balls and repeating the step of determining the effective multiplication factor until the effective multiplication factor is equal to the set value, to determine a node at which the experimental device is in critical safety.

4. The method of claim 3, wherein, After the determining the node at which the experimental device is in critical safety, the method further comprises: determining a target mass of the polyethylene balls corresponding to the node at which the experimental device is in critical safety, and determining a critical coolant loss amount of the experimental device based on the target mass; warning of the loss of coolant accident of the high temperature gas cooled reactor based on the critical coolant loss amount.

5. The method according to any one of claims 1-4, characterized in that, The monitoring reactivity of the core to obtain a reactivity result of the core comprises: monitoring a decay curve of neutron flux in the core based on a neutron counter to determine a decay constant of the neutron flux; determining the reactivity of the core based on the decay constant as the reactivity result.

6. An experimental apparatus for a loss of coolant accident of a high temperature gas cooled reactor, the experimental apparatus comprising: a core, a high-frequency pulsed neutron source and a neutron counter; the core comprises fuel balls and graphite balls that are uniformly mixed in equal numbers; the high-frequency pulsed neutron source is configured to emit high-frequency pulsed neutrons to the core; the neutron counter is configured to monitor a decay curve of neutron flux in the core.

7. A device for simulating a high temperature gas cooled reactor loss of coolant accident, characterized in that, The device comprises: a simulation module configured to place polyethylene balls of different masses uniformly in a core of an experimental device of a high temperature gas cooled reactor in order to simulate a loss of coolant accident of the experimental device, the experimental device being in a subcritical state; a monitoring module configured to emit high-frequency pulsed neutrons to the core of the experimental device and monitor reactivity of the core to obtain a reactivity result of the core; a verification module configured to verify critical safety of the experimental device in the loss of coolant accident in the subcritical state based on the reactivity result.

8. The apparatus of claim 7, wherein, The verification module is further configured to: determine an effective multiplication factor of the core under the influence of the polyethylene balls of different masses based on the reactivity result; verify critical safety of the experimental device in the loss of coolant accident in the subcritical state based on the effective multiplication factor and a set value.

9. The apparatus of claim 8, wherein, The verification module is further configured to: in response to the effective multiplication factor being less than the set value, increase the mass of the polyethylene balls and repeat the step of determining the effective multiplication factor until the effective multiplication factor is equal to the set value, to determine a node at which the experimental device is in critical safety. In response to the effective enrichment factor being less than a set value, the mass of the polyethylene sphere is increased, and the step of determining the effective enrichment factor is repeatedly performed until the effective enrichment factor is equal to the set value, to determine that the experimental device is at a point of critical safety.

10. The apparatus of claim 9, wherein, The verification module is further configured to: determine a target mass of the polyethylene sphere corresponding to the point of critical safety of the experimental device, and determine a critical water inflow of the experimental device based on the target mass; based on the critical water inflow, perform a pre-warning for a high-temperature gas cooled reactor water inflow accident.

11. The apparatus of any one of claims 7-10, wherein, The monitoring module is further configured to: based on the neutron counter, monitor a decay curve of the neutron flux in the core to determine a decay constant of the neutron flux; based on the decay constant, determine the reactivity of the core as the reactivity result.

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