CN113593740B

CN113593740B - Nuclear safety shell risk judging method and device, electronic equipment and storage medium

Info

Publication number: CN113593740B
Application number: CN202110747195.6A
Authority: CN
Inventors: 陈鹏; 贺东钰; 王政辉; 欧平文; 江娉婷; 罗勇
Original assignee: China General Nuclear Power Corp; China Nuclear Power Technology Research Institute Co Ltd; CGN Power Co Ltd
Current assignee: China General Nuclear Power Corp; China Nuclear Power Technology Research Institute Co Ltd; CGN Power Co Ltd
Priority date: 2021-07-01
Filing date: 2021-07-01
Publication date: 2024-02-27
Anticipated expiration: 2041-07-01
Also published as: CN113593740A

Abstract

The application relates to a nuclear containment risk judging method, a device, electronic equipment and a storage medium. The method comprises the following steps: acquiring a value of the pressure in the shell and the hydrogen share; when the pressure value and the hydrogen share meet the fitting relation of the pressure value and the hydrogen share in the shell, determining that the nuclear containment shell is at risk of damage; the method for determining the fitting relation between the in-shell pressure value and the hydrogen share comprises the following steps: acquiring running state parameters and system configuration parameters of the nuclear containment; based on a preset shell temperature value, a shell internal pressure value, an operating state parameter and a system configuration parameter, determining a fitting relation between the shell internal pressure value and the hydrogen share, wherein the fitting relation between the shell internal pressure value and the hydrogen share comprises the following steps: the fit relationship between the in-shell pressure value and the hydrogen combustion limit of the hydrogen share and the fit relationship between the in-shell pressure value and the nuclear containment of the hydrogen share are seriously threatened. The method can improve the accuracy of judging whether the nuclear containment has damage risk or not.

Description

Nuclear safety shell risk judging method and device, electronic equipment and storage medium

Technical Field

The present disclosure relates to the field of nuclear power technologies, and in particular, to a method and apparatus for determining risk of a nuclear containment, an electronic device, and a storage medium.

Background

With the development of nuclear power technology, a nuclear containment is the last barrier for defending nuclear safety, when a nuclear power station reactor has serious accidents, a great amount of hydrogen is generated due to the severe chemical reaction of zirconium alloy and water in the reactor, the hydrogen is accumulated in the nuclear containment, when the hydrogen concentration reaches a certain limit value, hydrogen combustion and hydrogen explosion can occur, and the combustion and explosion of the hydrogen can cause great threat to the structural integrity of a local compartment and the nuclear containment, and even cause the leakage of a great amount of radioactive substances.

In the prior art, according to a passive hydrogen concentration monitoring system of a nuclear power station and the like, after a serious accident occurs in the nuclear power station, the hydrogen combustion risk is evaluated so as to judge whether the nuclear containment has damage risk, and a basis is provided for serious accident management, etc., however, the accuracy is lower in judging whether the nuclear containment has damage risk.

Disclosure of Invention

In view of the above, it is desirable to provide a nuclear containment risk determination method, apparatus, electronic device, and storage medium that can improve the accuracy of nuclear containment damage risk determination.

A method of nuclear containment risk determination, the method comprising:

acquiring a pressure value in the shell;

obtaining the hydrogen share in the nuclear containment;

when the pressure value and the hydrogen share meet the fitting relation between the pressure value in the shell and the hydrogen share, determining that the nuclear containment shell is at risk of damage;

the method for determining the fitting relation between the in-shell pressure value and the hydrogen share comprises the following steps:

acquiring operation state parameters and system configuration parameters of the nuclear containment, wherein the operation state parameters are parameters used for representing the initial state of the nuclear containment, and the system configuration parameters are parameters used for representing the factory configuration of the nuclear containment;

based on a preset shell temperature value, the shell internal pressure value, an operating state parameter and a system configuration parameter, determining a fitting relation between the shell internal pressure value and the hydrogen share, wherein the fitting relation between the shell internal pressure value and the hydrogen share comprises the following steps: the fit relationship between the in-shell pressure value and the hydrogen combustion limit of the hydrogen share and the fit relationship between the in-shell pressure value and the nuclear containment of the hydrogen share are seriously threatened.

In one embodiment, the determining method of the preset shell temperature value includes:

and determining the preset shell temperature value based on the shell initial temperature value and the temperature value corresponding to the nuclear containment ultimate bearing pressure value.

In one embodiment, the system configuration parameters include shell exhaust fraction, shell free volume, shell failure probability, and the obtaining the hydrogen fraction in the containment shell includes:

obtaining the share of zirconium, the mass of zirconium and the molar mass of zirconium when the nuclear fuel cladding in the nuclear containment is subjected to oxidation reaction;

obtaining the hydrogen species mass within the nuclear fuel cladding based on the zirconium fraction, zirconium mass, zirconium molar mass, and the shell exhaust fraction;

obtaining a first steam pressure value, a first hydrogen pressure value and a first air pressure value, wherein the first steam pressure value is determined based on the preset shell temperature value, the shell internal pressure value, the first hydrogen pressure value is determined based on the containment free volume, the preset shell temperature value and the hydrogen content, and the first air pressure value is determined based on the air content in the nuclear containment, the preset shell temperature value and the containment free volume;

and when the relation between the pressure sum value and the in-shell pressure value meets a first preset relation, obtaining the hydrogen share in the nuclear containment shell based on the first hydrogen pressure value and the in-shell pressure value, wherein the pressure sum value is the sum of the first hydrogen pressure value, the first air pressure value and the first steam pressure value.

In one embodiment, the method further comprises:

and resetting the preset shell temperature value when the relation between the pressure sum value and the shell pressure value does not meet the first preset relation, and returning to the step of obtaining a first steam pressure value, a first hydrogen pressure value and a first air pressure value.

In one embodiment, the resetting the preset shell temperature value includes:

when the pressure sum value is larger than the shell pressure value, selecting a value larger than the preset shell temperature value of a first preset proportion, and resetting the value as the preset shell temperature value;

otherwise, selecting a value smaller than the preset shell temperature value of the second preset proportion, and resetting the value as the preset shell temperature value.

In one embodiment, the operation state parameters include a shell initial temperature value and a shell initial pressure value, and the determining manner of the air mass includes:

obtaining a shell initial air pressure value based on the shell initial temperature value and the shell initial pressure value;

based on the shell initial air pressure value, the shell free volume, and the shell exhaust fraction, an air content in the nuclear containment shell is obtained.

In one embodiment, the operation state parameters include a shell initial temperature value and a shell initial pressure value, the system configuration parameters include a shell exhaust share, a shell free volume and a shell failure probability, and the determination mode of the fitting relation between the shell pressure value and the hydrogen combustion limit value of the hydrogen share includes:

obtaining an air mass in a nuclear containment vessel based on the shell initial air pressure value, the shell free volume, the ideal gas constant, and the shell exhaust fraction;

obtaining a second steam pressure value, a second air pressure value, and a second hydrogen pressure value, the second steam pressure value being determined based on the preset shell temperature value, the shell internal pressure value, the second air pressure value being determined based on the amount of air in the nuclear containment shell, the preset shell temperature value, and the shell free volume, the second hydrogen pressure value being determined based on the shell internal pressure value, the second air pressure value, and the second steam pressure value;

and when the relation among the second hydrogen pressure value, the in-shell pressure value and the second steam pressure value meets a second preset relation, determining a hydrogen combustion limit fitting relation between the in-shell pressure value and the hydrogen share based on the second hydrogen pressure value and the in-shell pressure value.

In one embodiment, the method further comprises:

and resetting the preset shell temperature value when the relation among the second hydrogen pressure value, the shell internal pressure value and the second steam pressure value does not meet the second preset relation, and returning to the step of obtaining the second steam pressure value, the second air pressure value and the second hydrogen pressure value.

In one embodiment, resetting the preset shell temperature value when the relationship among the second hydrogen pressure value, the in-shell pressure value, and the second steam pressure value does not satisfy the second predetermined relationship includes:

determining a steam fraction based on the second steam pressure value, the in-shell pressure value;

determining a hydrogen fraction based on the second hydrogen pressure value;

and resetting the preset shell temperature value when the relationship between the hydrogen share and the steam share does not meet a second preset relationship.

In one embodiment, the resetting the preset shell temperature value includes:

when the steam share is larger than the hydrogen share, selecting a value smaller than the preset shell temperature value of a third preset proportion, and resetting the value as the preset shell temperature value;

Otherwise, selecting a value of the preset shell temperature value larger than the fourth preset proportion, and resetting the value as the preset shell temperature value.

In one embodiment, the operating state parameters include a shell initial temperature value, a shell initial pressure value, the system configuration parameters include a shell exhaust share, a shell free volume, a shell failure probability, and the determination of the fit relationship between the shell pressure value and the nuclear containment severe threat of the hydrogen share includes:

obtaining a nuclear containment failure margin based on the shell failure probability;

obtaining an air mass in the nuclear containment vessel based on the shell initial air pressure value, the shell free volume, the ideal gas constant, and the shell exhaust fraction;

obtaining a third vapor pressure value, a third air pressure value, and a third hydrogen pressure value, and a total pre-combustion gas mass, wherein the third vapor pressure value is determined based on the preset shell temperature value, the shell internal pressure value, the third air pressure value is determined based on the air mass in the nuclear containment shell, the preset shell temperature value, and the shell free volume, the third hydrogen pressure value is determined based on the shell internal pressure value, the third air pressure value, and the third vapor pressure value, and the total pre-combustion gas mass is determined based on the shell internal pressure value, the shell free volume, and the preset shell temperature value;

Obtaining a pre-combustion hydrogen mass and a pre-combustion steam mass, the pre-combustion hydrogen mass being determined based on the pre-combustion gas total mass, the in-shell pressure value, and the third hydrogen pressure value, the pre-combustion steam mass being obtained based on the pre-combustion gas total mass, the in-shell pressure value, and the third steam pressure value;

acquiring total mass of combusted gas, steam absorption energy and air absorption energy, wherein the total mass of combusted gas is obtained based on the total mass of combusted hydrogen and the total mass of combusted gas; the steam absorption energy is obtained based on the pre-combustion steam mass, the pre-combustion hydrogen mass, and the specific heat capacity of water; air absorption energy is obtained based on the shell air mass, the pre-combustion hydrogen mass, and the specific heat capacity of air;

and when a third predetermined relationship is met according to the relationship among the nuclear containment failure allowance, the total gas mass before combustion, the total gas mass after combustion, the preset shell temperature value, the hydrogen mass before combustion, the steam absorption energy, the air absorption energy and the preset shell temperature value, determining a nuclear containment serious threat fitting relationship between the in-shell pressure value and the hydrogen share based on the third hydrogen pressure value and the in-shell pressure value.

In one embodiment, the method further comprises:

and resetting the preset shell temperature value when the relation among the nuclear containment failure allowance, the total gas mass before combustion, the total gas mass after combustion, the preset shell temperature value, the total hydrogen gas mass before combustion, the steam absorption energy, the air absorption energy and the preset shell temperature value does not meet a third preset relation, and returning to the step of obtaining a third steam pressure value, a third air pressure value, a third hydrogen pressure value and the total hydrogen gas mass before combustion in the shell.

In one embodiment, resetting the preset shell temperature value when the relationship between the nuclear containment failure margin, the pre-combustion gas total mass, the post-combustion gas total mass, the preset shell temperature value and the pre-combustion hydrogen gas mass, the steam absorption energy, the air absorption energy, the preset shell temperature value does not satisfy a third predetermined relationship comprises:

determining a first related parameter of the gas in the shell before and after combustion based on the nuclear containment failure allowance, the total mass of the gas before combustion, the total mass of the gas after combustion and the preset shell temperature value;

Determining second related parameters before and after combustion of the gas in the second shell of the gas in the shell based on the hydrogen gas mass before combustion, the steam absorption energy, the air absorption energy and the preset shell temperature value;

and resetting the preset shell temperature value when the relation between the first related parameter and the second related parameter does not meet a third preset relation.

In one embodiment, the resetting the preset shell temperature value includes:

when the first related parameter is larger than the second related parameter, selecting a value smaller than the preset shell temperature value of a fifth preset proportion, and resetting the value as the preset shell temperature value;

otherwise, selecting a value of the preset shell temperature value larger than the sixth preset proportion, and resetting the value as the preset shell temperature value.

A nuclear containment risk assessment apparatus, the apparatus comprising:

the pressure value acquisition module is used for acquiring the pressure value in the shell;

the hydrogen share acquisition module is used for acquiring the hydrogen share in the nuclear containment;

the nuclear containment shell damage risk judging module is used for determining that the nuclear containment shell has damage risk when the pressure value and the hydrogen share meet the fitting relation of the pressure value in the shell and the hydrogen share;

The fitting relation determining module is used for obtaining the running state parameters and the system configuration parameters of the nuclear containment, wherein the running state parameters are parameters used for representing the initial state of the nuclear containment, and the system configuration parameters are parameters used for representing the factory configuration of the nuclear containment; based on a preset shell temperature value, the shell internal pressure value, an operating state parameter and a system configuration parameter, determining a fitting relation between the shell internal pressure value and the hydrogen share, wherein the fitting relation between the shell internal pressure value and the hydrogen share comprises the following steps: the fit relationship between the in-shell pressure value and the hydrogen combustion limit of the hydrogen share and the fit relationship between the in-shell pressure value and the nuclear containment of the hydrogen share are seriously threatened.

An electronic device comprising a memory storing a computer program and a processor implementing the steps of the above-described nuclear containment risk determination method when the processor executes the computer program.

A computer readable storage medium having stored thereon a computer program which, when executed by a processor, implements the steps of the above-described nuclear containment risk determination method.

According to the nuclear containment risk judging method, the device, the electronic equipment and the storage medium, the pressure value in the shell and the hydrogen share in the nuclear containment are obtained, so that when the pressure value and the hydrogen share meet the fitting relation between the pressure value in the shell and the hydrogen share, the damage risk of the nuclear containment is determined, wherein the fitting relation between the pressure value in the shell and the hydrogen share is determined by obtaining the running state parameter and the system configuration parameter of the nuclear containment and combining the preset temperature value in the shell and the pressure value in the shell, and the fitting relation between the pressure value in the shell and the hydrogen share comprises the fitting relation between the pressure value in the shell and the hydrogen combustion limit value of the hydrogen share and the fitting relation between the pressure value in the shell and the serious threat of the nuclear containment of the hydrogen share. The method can improve the accuracy of judging whether the nuclear containment shell has damage risk.

Drawings

FIG. 1 is a diagram of an application environment for a method of risk assessment for a nuclear containment in one embodiment;

FIG. 2 is a flow chart of a method for determining risk of a nuclear containment in one embodiment;

FIG. 3 is a flowchart of a method for determining risk of a nuclear containment in another embodiment;

FIG. 4 is a graph of a fit relationship between the in-shell pressure value and the hydrogen gas fraction in a nuclear containment risk determination method according to one embodiment;

FIG. 5 is a block diagram of a nuclear containment risk assessment apparatus in one embodiment;

FIG. 6 is an internal block diagram of an electronic device in one embodiment;

fig. 7 is an internal structural diagram of an electronic device in one embodiment.

Detailed Description

In order to make the objects, technical solutions and advantages of the present application more apparent, the present application will be further described in detail with reference to the accompanying drawings and examples. It should be understood that the specific embodiments described herein are for purposes of illustration only and are not intended to limit the present application.

The nuclear containment risk judging method provided by the application can be applied to an application environment shown in fig. 1. The application environment relates to the electronic equipment 102 and the nuclear containment 104 at the same time, wherein the electronic equipment 102 is intelligent control equipment capable of realizing operation functions, communication functions, alarm functions and the like, the nuclear containment 104 is a protection structure of a nuclear power plant reactor main factory building, and a pressure measuring instrument, a hydrogen measuring instrument, a temperature measuring instrument, a reactor, a steam generator, a main circulating pump, a pressure stabilizer, inlet and outlet pipeline valves of a coolant and the like are arranged in the nuclear containment 104.

In one embodiment, when a serious accident occurs in a nuclear power plant, core debris in the reactor falls into a reactor cavity, nuclear fuel (zirconium alloy) in the reactor reacts with concrete to generate a large amount of hydrogen, when the hydrogen content reaches a certain index, the hydrogen is exploded and releases a large amount of energy to act on the nuclear containment 104 in the form of pressure and temperature load, a higher pressure peak is formed in a very short time, and the structure of the nuclear containment 104 is damaged instantaneously.

In one embodiment, the electronic device 102 obtains the in-shell pressure value of the nuclear containment 104, and the hydrogen content within the nuclear containment; when the pressure value and the hydrogen share meet the fitting relation between the in-shell pressure value and the hydrogen share, determining that the nuclear containment shell is at risk of damage, wherein the determining method of the fitting relation between the in-shell pressure value and the hydrogen share comprises the following steps: acquiring an operation state parameter and a system configuration parameter of the nuclear containment, wherein the operation state parameter is a parameter for representing the initial state of the nuclear containment, the system configuration parameter is a parameter for representing the factory configuration of the nuclear containment, and the fitting relation between the in-shell pressure value and the hydrogen share is determined based on a preset shell temperature value, the in-shell pressure value, the operation state parameter and the system configuration parameter, and the fitting relation between the in-shell pressure value and the hydrogen share comprises: the fit relationship between the in-shell pressure value and the hydrogen combustion limit of the hydrogen share and the fit relationship between the in-shell pressure value and the nuclear containment of the hydrogen share are seriously threatened. The electronic device 102 may be a terminal, or may be a server, where the terminal may be, but is not limited to, various personal computers, notebook computers, smart phones, tablet computers, and portable wearable devices, and the server may be implemented by an independent server or a server cluster formed by a plurality of servers.

In one embodiment, as shown in fig. 2, a method for judging risk of a nuclear containment is provided, and the method is applied to the electronic device in fig. 1 for illustration, and includes the following steps:

step S202, obtaining the pressure value in the shell.

The term "shell" refers to the inside of a containment shell, and the term "shell" as used hereinafter refers to the inside of a containment shell. The in-shell pressure value refers to a pressure value in a nuclear containment vessel, wherein the in-shell pressure value can be obtained through a pressure measuring instrument installed in the vessel, or an initial pressure value in the vessel can be used as a reference value, and a value is set as the in-shell pressure value according to the actual situation of the in-shell pressure value, for example, after a serious accident occurs in a nuclear power plant, a value larger than the initial pressure value in the vessel can be set as the in-shell pressure value.

Step S204, obtaining the hydrogen share in the nuclear containment.

The hydrogen share refers to the ratio of the mole fraction of hydrogen in the nuclear containment to the mole fraction of total gas, and can be obtained by a hydrogen measuring instrument arranged in the nuclear containment, or by calculating the proportion of nuclear fuel (mainly zirconium) in a set nuclear fuel cladding in the shell. In the embodiments, when the calculation of the mole fraction of the gas is concerned, it may be assumed that the ideal gas characteristic is satisfied, and the mole fraction of the gas pressure is equal to the volume fraction in the ideal gas characteristic, so the mole fraction of the hydrogen gas may be numerically equal to the ratio of the pressures, and thus, when the calculation of the share of the hydrogen gas is concerned, the ratio of the pressures is replaced in the embodiments described below.

Step S206, determining that the nuclear containment shell is at risk of breakage when the pressure value and the hydrogen share satisfy the fitting relationship between the in-shell pressure value and the hydrogen share.

The fitting relation between the in-shell pressure value and the hydrogen share can be a curve obtained by fitting the in-shell pressure value and the hydrogen share of the in-shell pressure value, and when the pressure value and the hydrogen share meet the fitting relation between the in-shell pressure value and the hydrogen share, the risk of damage of the nuclear containment shell can be determined.

In one embodiment, when any parameters in the shell, such as pressure, gas mass, etc., are calculated, the following three conditions are satisfied, namely, no consideration is given to any dehydrogenation action (such as the action of a hydrogen synthesizer) in the shell, the steam in the shell is in a saturated state, and the case of the shell with overheat condition is also the case, and the gas in the shell is uniformly distributed, so that the condition that different gas components are accumulated in the compartment is not generated.

In one embodiment, as shown in fig. 3, a process for determining a fit relationship between a pressure value of a nuclear containment and a hydrogen gas share is provided, and the process is applied to the electronic device 102 in fig. 1, for example, and includes the following steps:

Step S302, acquiring operation state parameters and system configuration parameters of the nuclear containment, wherein the operation state parameters are parameters for representing the initial state of the nuclear containment, and the system configuration parameters are parameters for representing the factory configuration of the nuclear containment.

The running state parameters of the core-shell refer to parameters which can represent the initial state of the core-shell, such as a shell initial temperature value and a shell initial pressure value, and the system configuration parameters refer to defined parameters such as shell free volume, shell failure probability and the like when the design of the core-shell is carried out.

Step S304, based on a preset shell temperature value, the shell internal pressure value, an operation state parameter and a system configuration parameter, determining a fitting relation between the shell internal pressure value and the hydrogen share, wherein the fitting relation between the shell internal pressure value and the hydrogen share comprises: the fit relationship between the in-shell pressure value and the hydrogen combustion limit of the hydrogen share and the fit relationship between the in-shell pressure value and the nuclear containment of the hydrogen share are seriously threatened.

In one embodiment, the preset shell temperature value may be determined according to a shell initial temperature value and a temperature value corresponding to a core containment limit bearing pressure value, and a fitting relationship between the shell internal pressure value and a hydrogen share may be determined according to the preset shell temperature value, the shell internal pressure value, an operation state parameter and a system configuration parameter, where the fitting relationship between the shell internal pressure value and the hydrogen share includes a fitting relationship between the shell internal pressure value and a hydrogen combustion limit of the hydrogen share, and a fitting relationship between the shell internal pressure value and a core containment serious threat of the hydrogen share.

In the nuclear containment risk judging method, the shell internal pressure value and the hydrogen share in the nuclear containment are obtained, so that when the pressure value and the hydrogen share meet the fitting relation of the shell internal pressure value and the hydrogen share, the damage risk of the nuclear containment is determined, wherein the fitting relation of the shell internal pressure value and the hydrogen share is determined by obtaining the running state parameter and the system configuration parameter of the nuclear containment and combining the preset shell temperature value and the shell internal pressure value, and the fitting relation of the shell internal pressure value and the hydrogen share comprises the fitting relation of the shell internal pressure value and the hydrogen combustion limit value of the hydrogen share and the fitting relation of the shell internal pressure value and the serious threat of the nuclear containment of the hydrogen share. The method can improve the accuracy of judging whether the nuclear containment shell has damage risk.

obtaining the share of zirconium, the mass of zirconium and the molar mass of zirconium when the nuclear fuel cladding in the nuclear containment is subjected to oxidation reaction; obtaining the hydrogen species mass within the nuclear fuel cladding based on the zirconium fraction, zirconium mass, zirconium molar mass, and the shell exhaust fraction; obtaining a first steam pressure value, a first hydrogen pressure value and a first air pressure value, wherein the first steam pressure value is determined based on the preset shell temperature value, the shell internal pressure value, the first hydrogen pressure value is determined based on the containment free volume, the preset shell temperature value and the hydrogen content, and the first air pressure value is determined based on the air content in the nuclear containment, the preset shell temperature value and the containment free volume; and when the relation between the pressure sum value and the in-shell pressure value meets a first preset relation, obtaining the hydrogen share in the nuclear containment shell based on the first hydrogen pressure value and the in-shell pressure value, wherein the pressure sum value is the sum of the first hydrogen pressure value, the first air pressure value and the first steam pressure value.

When a serious accident occurs in a nuclear power plant, core debris in a reactor falls into a reactor cavity, and nuclear fuel (zirconium alloy) in the core reacts with concrete to generate hydrogen. The nuclear fuel, mainly zirconium, in the nuclear fuel cladding undergoes oxidation reactions to produce a large amount of hydrogen.

In one embodiment, the hydrogen content in the nuclear fuel cladding may be obtained by obtaining a zirconium fraction, a zirconium mass, a zirconium molar mass, etc., based on the zirconium fraction, the zirconium mass, the zirconium molar mass, and the shell exhaust fraction, with the calculation formula: n is n _H2 ＝2×R _x M/M _zr X (1-vent), wherein R _x Represents the zirconium content in the oxidation reaction, which may be set to 0.25, 0.50, 0.75 or 1.0), etc., M represents the mass of zirconium, M _zr Represents the mass per mole of zirconium and vent represents the shell off-gas fraction.

In one embodiment, the physical property table of the water vapor can be searched according to a preset shell temperature value and a preset shell pressure value, so as to obtain a first vapor pressure value.

In one embodiment, the first hydrogen pressure value may be obtained by the following formula: p (P) _H2 ＝(n _H2 X (R x (T+273.15)/Volume), where P _H2 Representing the first hydrogen pressure value, volume Representing the free volume of the containment, T representing the preset shell temperature value, n _H2 Indicating the amount of hydrogen gas.

In one embodiment, the first air pressure, P, may be obtained by the following equation _air ＝(n _air +n _MccI )×R×(T+273.15)/Volume，n _air Represents the air content, n _MCCI Non-flammable, non-condensable gases (e.g., carbon monoxide, carbon dioxide, etc.) are released during the core and concrete reaction, but in severe accidents, the amounts of carbon monoxide and carbon dioxide produced are small and therefore essentially negligible.

In one embodiment, the first predetermined relationship refers to a relationship between a preset pressure and a value of the in-shell pressure, for example, the difference between the pressure and the value of the in-shell pressure is within a certain range, or the pressure and the value of the in-shell pressure are equal to the value of the in-shell pressure.

In one embodiment, the first predetermined relationship is that the pressure sum value needs to be equal to the in-shell pressure value, specifically expressed as: p=p _air +P _S +P _H2 Wherein P is _air Representing a first air pressure value, P _s Representing a first vapor pressure value, P _H2 The first hydrogen pressure value is represented, and P represents the in-shell pressure value.

In one embodiment, when the pressure sum and the in-shell pressure value satisfy a first predetermined relationship, the hydrogen share may be obtained according to the first hydrogen pressure value and the in-shell pressure value, where the specific formula is: p (P) _{Hydrogen fraction} ＝P _H2 /P。

In one embodiment, the method further comprises:

and resetting the preset shell temperature value when the relation between the pressure and the value and the pressure value in the shell does not meet the first preset relation, and returning to the step of obtaining a first steam pressure value, a first hydrogen pressure value and a first air pressure value.

When the relation between the pressure and the value and the pressure value in the shell does not meet the first preset relation, the preset shell temperature value needs to be reset, and the preset shell temperature value is involved in calculating the first steam pressure value, the first air pressure value and the first hydrogen pressure value, so that the steps of returning the first steam pressure value, the first hydrogen pressure value and the first air pressure value are needed after the preset shell temperature value is reset. Thus, by the method, after the shell temperature value is reset, the calculation can be unfolded based on the new preset shell temperature value.

In one embodiment, the resetting the preset shell temperature value includes:

The first preset proportion and the second preset proportion can be the same or different, and can be adjusted according to actual conditions. In one embodiment, the first preset ratio is equal to the second preset ratio, for example, the first preset ratio and the second preset ratio are both half, and when the pressure sum is greater than the in-shell pressure value, a value greater than half of the preset shell temperature value is selected, reset to the preset shell temperature value, and when the pressure sum is less than the in-shell pressure value, a value less than half of the preset shell temperature value is selected, and reset to the preset shell temperature value. So that the preset shell temperature value can be reset by the above-described method.

obtaining a shell initial air pressure value based on a shell initial temperature value and the shell initial pressure value;

Wherein the operating state parameters may include a shell initial temperature value, a shell initial pressure value, etc., according to the shell initial temperature value, the shellThe initial pressure value is searched for a steam physical table, a shell initial steam pressure value can be obtained, and after the shell initial steam pressure value is obtained, a shell initial air pressure value is obtained according to the shell initial steam pressure value and the shell initial pressure value, wherein the calculation formula is as follows: p (P) _a1 ＝P ₁ -P _s1 ，P ₁ Representing the initial pressure value of the shell, P _S1 Indicating the initial vapor pressure value, P, of the shell _a1 Representing the initial air pressure value of the shell.

After the initial air pressure value of the shell is obtained, the air mass can be calculated, and the calculation formula is as follows: n is n _air ＝1.1×(1-vent)×(P _a1 X Volume)/(r× (t+273.15)), wherein vent represents a shell exhaust gas fraction, which can be determined according to the actual exhaust conditions of the nuclear power plant, R represents an ideal gas constant, the value is 8.31, T represents a shell preset temperature value, and Volume represents a shell free Volume. The air mass can be calculated by the method, and the following embodiments all adopt the formula to calculate when the air mass is calculated.

Obtaining a shell initial air pressure value based on the shell initial temperature value and the shell initial pressure value; obtaining an air mass in a nuclear containment vessel based on the shell initial air pressure value, the shell free volume, and the shell exhaust fraction; obtaining a second steam pressure value, a second air pressure value, and a second hydrogen pressure value, the second steam pressure value being determined based on the preset shell temperature value, the shell internal pressure value, the second air pressure value being determined based on the amount of air in the nuclear containment shell, the preset shell temperature value, and the shell free volume, the second hydrogen pressure value being determined based on the shell internal pressure value, the second air pressure value, and the second steam pressure value; and when the relation among the second hydrogen pressure value, the in-shell pressure value and the second steam pressure value meets a second preset relation, determining a hydrogen combustion limit fitting relation between the in-shell pressure value and the hydrogen share based on the second hydrogen pressure value and the in-shell pressure value.

In one embodiment, the air content in the nuclear containment vessel is calculated and obtained, and then a second steam pressure value, a second air pressure value and a second hydrogen pressure value are calculated and obtained, wherein the second steam pressure value can be obtained by checking a steam property table according to a preset shell temperature value and a preset shell pressure value, and when the second air pressure value is calculated, the calculation formula is as follows: p (P) _ainert ＝(n _air +n _MccI ) X R x (T+273.15)/Volume, where P _ainert Representing a second air pressure value, n _air The air content is represented by R, the ideal gas constant is represented by R, the value of R is 8.31, T represents the preset shell temperature value, the Volume shell free Volume is represented by n _MCCI Non-flammable, non-condensable gases (e.g., carbon monoxide, carbon dioxide, etc.) are released during the core and concrete reaction, but in severe accidents, the amounts of carbon monoxide and carbon dioxide produced are small and therefore essentially negligible. In calculating the second hydrogen pressure value, the calculation formula is: p=p _ainert +P _sinert +P _Hinert Wherein P represents the value of the in-shell pressure, P _ainert Representing a second air pressure value, P _sinert Representing a second vapor pressure value, P _Hinert Representing a second hydrogen pressure value.

In one embodiment, resetting the preset shell temperature value when the relationship among the second hydrogen pressure value, the in-shell pressure value, and the second steam pressure value does not satisfy the second predetermined relationship includes: determining a hydrogen fraction based on the second hydrogen pressure value, the in-shell pressure value; determining a steam fraction based on the second steam pressure value; and resetting the preset shell temperature value when the relationship between the hydrogen share and the steam share does not meet a second preset relationship.

In one embodiment, the second predetermined relationship represents a predetermined second hydrogen pressure value, an in-shell pressure value, and a second vapor pressureThe relationship between the force values, when the second predetermined relationship is satisfied, may indicate that the hydrogen fraction within the shell reaches the combustion limit. The second hydrogen pressure value can also be calculated conventionally (for example, by performing operations such as addition, subtraction, multiplication, division, etc. with a constant) to obtain a steam fraction, and if the calculated hydrogen fraction and the calculated steam fraction are equal, or the difference is within a certain range, the second predetermined relationship is satisfied, where the calculation formula is: wherein P represents the value of the in-shell pressure, P _sinert Representing a second vapor pressure value, P _Hinert Representing a second hydrogen pressure value. When it is determined that the second predetermined relationship is satisfied, the hydrogen gas fraction may be calculated by the following formula: p (P) _{Hydrogen fraction} ＝P _Hinert P. After the hydrogen share is calculated, a fitting relation between the pressure value in the shell and the hydrogen combustion limit value of the hydrogen share can be obtained when the hydrogen share in the shell reaches the combustion limit value.

In one embodiment, the method further comprises: and resetting the preset shell temperature value when the relation among the second hydrogen pressure value, the shell internal pressure value and the second steam pressure value does not meet the second preset relation, and returning to the step of obtaining the second steam pressure value, the second air pressure value and the second hydrogen pressure value.

When the relationship among the second hydrogen pressure value, the in-shell pressure value and the second steam pressure value does not meet the second predetermined relationship, the preset shell temperature value needs to be reset, and the preset shell temperature value is involved in calculating the first steam pressure value, the first air pressure value and the first hydrogen pressure value, so that the step of returning to obtain the second steam pressure value, the second air pressure value and the second hydrogen pressure value is needed after the preset shell temperature value is reset. Thus, by the method, after the shell temperature value is reset, the calculation can be unfolded based on the new preset shell temperature value.

In one embodiment, the resetting the preset shell temperature value includes:

when the steam share is larger than the hydrogen share, selecting a value smaller than the preset shell temperature value of a third preset proportion, and resetting the value as the preset shell temperature value; otherwise, selecting a value larger than the preset shell temperature value of the fourth preset proportion, and resetting the value as the preset shell temperature value.

The third preset proportion and the fourth preset proportion can be the same or different, and can be adjusted according to actual conditions. In one embodiment, the third preset proportion is equal to the fourth preset proportion, for example, the third preset proportion and the fourth preset proportion are both half of the values, and when the steam share is greater than the hydrogen share, a value greater than half of the preset shell temperature value is selected, and the preset shell temperature value is reset. So that the preset shell temperature value can be reset by the above-described method.

Obtaining a pre-combustion hydrogen mass and a pre-combustion steam mass, the pre-combustion hydrogen mass being determined based on the pre-combustion gas total mass, the in-shell pressure value, and the third hydrogen pressure value, the pre-combustion steam mass being obtained based on the pre-combustion gas total mass, the in-shell pressure value, and the third steam pressure value; acquiring total mass of combusted gas, steam absorption energy and air absorption energy, wherein the total mass of combusted gas is obtained based on the total mass of combusted hydrogen and the total mass of combusted gas; the steam absorption energy is obtained based on the pre-combustion steam mass, the pre-combustion hydrogen mass, and the specific heat capacity of water; air absorption energy is obtained based on the shell air mass, the pre-combustion hydrogen mass, and the specific heat capacity of air; and when the relation among the nuclear containment failure allowance, the total gas mass before combustion, the total gas mass after combustion, the preset shell temperature value, the hydrogen mass before combustion, the steam absorption energy and the air absorption energy meets a third preset relation, determining a nuclear containment serious threat fitting relation between the in-shell pressure value and the hydrogen share based on the third hydrogen pressure value and the in-shell pressure value.

In one embodiment, the shell failure probability belongs to a containment system configuration parameter, the core containment failure margin can be used for representing the degree to which the core containment can bear pressure, and when the core containment failure margin is calculated, the calculation formula is as follows: m is M _argin ＝P _fair /P，M _argin Representing a nuclear containment failure margin, P _fail And the value obtained by subtracting 10Pa from the pressure value in the shell when the value is equal to 5% of the shell failure probability, wherein P represents the value of the pressure in the shell.

In one embodimentThe third preset relation represents the preset relation among the nuclear containment failure allowance, the total mass of gas before combustion, the total mass of gas after combustion, the preset shell temperature value, the hydrogen mass before combustion, the steam absorption energy, the air absorption energy and the preset shell temperature value, when the third preset relation is met, the condition that the structure of the nuclear containment reaches the damage condition can be represented, and when the structure of the nuclear containment reaches the damage condition, a fit relation curve of the pressure value in the shell and the serious threat of the nuclear containment of the hydrogen share can be obtained. Firstly, calculating to obtain the air content in the nuclear containment, then calculating a third steam pressure value, a third air pressure value, a third hydrogen pressure value and the total gas content before combustion, wherein the third steam pressure value can be obtained by checking a steam property table according to a preset shell temperature value and a preset shell pressure value, and a calculation formula is as follows: P _afail Represents a third air pressure value, n _air Representing the air mass n _MCCI The reactor core is characterized in that the reactor core and concrete are subjected to reaction to release of nonflammable and non-condensable gases (such as carbon monoxide, carbon dioxide and the like), but in serious accidents, the generated carbon monoxide and carbon dioxide are small, so that the reactor core is basically negligible, R represents an ideal gas constant, the value of R can be 8.31, T represents a preset shell temperature value, and the free Volume of a Volume shell is realized. In calculating the third hydrogen pressure value, the calculation formula is: p=p _afail +P _sfail +P _Hfail Wherein P is _sfail Representing a third vapor pressure value, P _Hfair A third hydrogen pressure value is indicated.

In one embodiment, the total mass of the gas before combustion refers to the total mass of the gas before combustion of hydrogen in the shell, and the calculation formula is as follows: n is n _pre = (P x Volume)/(r× (t+273.15), where n _pre The total mass of the gas before combustion is represented by P, the value of the pressure in the shell is represented by Volume, the free Volume of the shell is represented by Volume, and the preset value of the temperature of the shell is represented by T.

In one embodiment, the pre-combustion hydrogen content represents the pre-combustion hydrogen content of the hydrogen in the shellThe mass and the calculation formula are as follows: n is n _Hfail ＝P _Hfail /P×n _pre Wherein n is _Hfail Indicating the hydrogen content before combustion, P _Hfail Represents the third hydrogen pressure, P represents the pressure value in the shell, n _pre Indicating the total mass of gas before combustion.

In one embodiment, the pre-combustion vapor mass represents the pre-combustion vapor mass of hydrogen in the shell, and the calculation formula is: n is n _sfail ＝P _sfail /P×n _pre Wherein n is _sfail Indicating the steam mass before combustion, P _sfail Represents the third vapor pressure, P represents the pressure value in the shell, n _pre Indicating the total mass of gas before combustion.

In one embodiment, the total mass of the combusted gas refers to the total mass of the combusted gas of the hydrogen in the shell, and the calculation formula is as follows: n is n _post ＝n _pre -0.5×n _Hfail Wherein n is _post Indicating the total mass of the gas after combustion, n _pre Indicating the total mass of the gas before combustion, n _Hfail Indicating the amount of hydrogen species before combustion.

In one embodiment, the calculation of the steam absorption energy is as follows: team= (n) _sfail +n _Hfail )×C _vs X 18, where steam represents steam absorption energy, n _sfail Indicating the amount of steam before combustion, n _Hfail Indicating the hydrogen content before combustion, C _vs Represents the specific heat of water.

In one embodiment, the air absorption energy is calculated as: air= (n) _air +n _Hfail )×C _va 28, wherein air represents air absorption energy, n _air Represents the air content of the shell, n _Hfail Indicating the hydrogen content before combustion, C _va Represents the specific heat of air.

In one embodiment, the method further comprises: and resetting the preset shell temperature value when the relation among the nuclear containment failure allowance, the total gas mass before combustion, the total gas mass after combustion, the preset shell temperature value, the hydrogen gas mass before combustion, the steam absorption energy, the air absorption energy and the preset shell temperature value does not meet a third preset relation, and returning to the step of obtaining a third steam pressure value, a third air pressure value, a third hydrogen pressure value and the total gas mass before combustion of hydrogen in the shell.

In one embodiment, resetting the preset shell temperature value when the relationship between the nuclear containment failure margin, the pre-combustion gas total mass, the post-combustion gas total mass, the preset shell temperature value and the pre-combustion hydrogen mass, the steam absorption energy, the air absorption energy, the preset shell temperature value does not satisfy a third predetermined relationship comprises:

The calculation formula for calculating the first related parameter and the second related parameter is as follows: wherein Margin represents a nuclear containment failure Margin, n _pre Indicating the total mass of the gas before combustion, n _post Representing the total mass of the gas after combustion, T representing a preset shell temperature value, Q _r Represents the specific heat of air, n _Hfail Indicative of the hydrogen mass prior to combustion, steam indicative of steam absorption energy, air indicative of air absorption energy.

In one embodiment, the resetting the preset shell temperature value includes:

The fifth preset proportion and the sixth preset proportion may be the same or different, and may be adjusted according to actual conditions. In one embodiment, the fifth preset proportion is equal to the sixth preset proportion, for example, the fifth preset proportion and the sixth preset proportion are both half of the values, and when the third preset relation is not satisfied, a value smaller than half of the preset shell temperature value is selected and reset to the preset shell temperature value. So that the preset shell temperature value can be reset by the above-described method.

In one embodiment, as shown in fig. 4, a graph of a fitting relationship between an in-shell pressure value and a hydrogen portion in a nuclear containment risk judging method in a specific embodiment is shown, and it can be seen from the graph that the fitting relationship between the in-shell pressure value and the hydrogen portion includes a hydrogen combustion limit fitting relationship between the in-shell pressure value and the hydrogen portion, and a nuclear containment serious threat fitting relationship between the in-shell pressure value and the hydrogen portion, wherein a curve of the in-shell pressure value and the hydrogen portion in an inverse proportion state is a hydrogen combustion limit fitting curve, a curve of the in-shell pressure value and the hydrogen portion in a positive proportion state is a nuclear containment serious threat fitting curve of the pressure value and the hydrogen portion, and 3.2bar (pressure unit) and 7.5% (hydrogen portion) are intersections of the hydrogen combustion limit fitting curve and the nuclear containment serious threat fitting curve. When a serious accident occurs in a nuclear power plant, hydrogen shares generated by zirconium shares of different proportions are different, corresponding hydrogen shares are corresponding to the corresponding hydrogen shares under different shell pressure values, a fitting curve of the internal shell pressure value and the hydrogen shares under the zirconium shares of different proportions can be fitted under the serious accident by the different shell pressure values and the corresponding hydrogen shares, the fitting curve of the internal shell pressure value and the hydrogen shares under the zirconium shares of different proportions is determined according to the intersection point (3.2 and 7.5%) under the zirconium shares of different proportions, and therefore whether the generated hydrogen shares can cause structural damage of a containment, for example, when any point in the fitting curve of the internal shell pressure value and the hydrogen shares under the zirconium shares of different proportions belongs to any threat in the fitting curve of the hydrogen combustion limit value and the serious containment, the meeting relation of the internal shell pressure value and the hydrogen shares is determined, and the risk of breakage of the nuclear containment can be determined, wherein the intersection point range is determined according to the intersection point (3.2 and 7.5%) as shown in fig. 4, and the fitting curve of the hydrogen combustion limit value is a large threat value in the curve of the pressure bar of the nuclear containment and the pressure bar of the containment is a large part of the curve when the fitting curve is a curve of the nuclear pressure bar of 1.2 bar.

It should be understood that, although the steps in the flowcharts of fig. 2-3 are shown in order as indicated by the arrows, these steps are not necessarily performed in order as indicated by the arrows. The steps are not strictly limited to the order of execution unless explicitly recited herein, and the steps may be executed in other orders. Moreover, at least some of the steps in fig. 2-3 may include multiple steps or stages that are not necessarily performed at the same time, but may be performed at different times, nor does the order in which the steps or stages are performed necessarily performed in sequence, but may be performed alternately or alternately with at least a portion of the steps or stages in other steps or other steps.

In one embodiment, as shown in fig. 5, there is provided a nuclear containment risk judging device, including: the device comprises a pressure value acquisition module, a hydrogen share acquisition module, a nuclear containment damage risk judgment module and a fitting relation determination module, wherein:

the pressure value acquisition module 502 is configured to acquire a pressure value in the shell.

A hydrogen fraction obtaining module 504, configured to obtain a hydrogen fraction in the nuclear containment.

And the nuclear containment breakage risk judging module 506 is configured to determine that the nuclear containment is at a breakage risk when the pressure value and the hydrogen share satisfy a fitting relationship between the pressure value and the hydrogen share.

The fitting relation determining module 508 is configured to obtain an operation state parameter and a system configuration parameter of the core-shell, where the operation state parameter is a parameter for representing an initial state of the core-shell, and the system configuration parameter is a parameter for representing factory configuration of the core-shell; based on a preset shell temperature value, the shell internal pressure value, an operating state parameter and a system configuration parameter, determining a fitting relation between the shell internal pressure value and the hydrogen share, wherein the fitting relation between the shell internal pressure value and the hydrogen share comprises the following steps: the fit relationship between the in-shell pressure value and the hydrogen combustion limit of the hydrogen share and the fit relationship between the in-shell pressure value and the nuclear containment of the hydrogen share are seriously threatened.

In one embodiment, the apparatus further comprises:

the preset shell temperature value determining module is used for determining the preset shell temperature value based on the shell initial temperature value and the temperature value corresponding to the nuclear containment ultimate bearing pressure value.

The preset shell temperature value determining module is further configured to reset the preset shell temperature value when the relationship between the pressure sum value and the in-shell pressure value does not satisfy the first predetermined relationship.

The preset shell temperature value determining module is further used for selecting a value larger than a preset shell temperature value of a first preset proportion and resetting the value as the preset shell temperature value when the pressure sum value is larger than the shell pressure value; otherwise, selecting a value smaller than the preset shell temperature value of the second preset proportion, and resetting the value as the preset shell temperature value.

The preset shell temperature value determining module is further configured to reset the preset shell temperature value when the relationship among the second hydrogen pressure value, the in-shell pressure value, and the second steam pressure value does not satisfy the second predetermined relationship.

The preset shell temperature value determining module is further used for determining the steam share based on the second steam pressure value and the shell pressure value; determining a hydrogen fraction based on the second hydrogen pressure value; and resetting the preset shell temperature value when the relationship between the hydrogen share and the steam share does not meet a second preset relationship.

The preset shell temperature value determining module is further used for selecting a value smaller than the preset shell temperature value of a third preset proportion and resetting the value as the preset shell temperature value when the steam share is larger than the hydrogen share; otherwise, selecting a value larger than the preset shell temperature value of the fourth preset proportion, and resetting the value as the preset shell temperature value.

The preset shell temperature value determining module is further configured to reset the preset shell temperature value when a relationship between the nuclear containment failure allowance, the total gas mass before combustion, the total gas mass after combustion, the preset shell temperature value and the total hydrogen mass before combustion, the steam absorption energy, the air absorption energy, and the preset shell temperature value does not satisfy a third predetermined relationship.

The preset shell temperature value determining module is further used for determining a first related parameter before and after the combustion of the gas in the shell based on the nuclear containment failure allowance, the total mass of the gas before combustion, the total mass of the gas after combustion and the preset shell temperature value; determining second related parameters before and after combustion of the gas in the second shell of the gas in the shell based on the hydrogen gas mass before combustion, the steam absorption energy, the air absorption energy and the preset shell temperature value; and resetting the preset shell temperature value when the relation between the first related parameter and the second related parameter does not meet a third preset relation.

The preset shell temperature value determining module is further configured to select a value of the preset shell temperature value smaller than a fifth preset proportion when the first related parameter is larger than the second related parameter, reset the value to the preset shell temperature value, and otherwise select a value of the preset shell temperature value larger than the sixth preset proportion, reset the value to the preset shell temperature value.

A determination module of air mass for obtaining a shell initial air pressure value based on the shell initial temperature value, the shell initial pressure value; based on the shell initial air pressure value, the shell free volume, and the shell exhaust fraction, an air content in the nuclear containment shell is obtained.

In one embodiment, the hydrogen share obtaining module is used for obtaining the share of zirconium, the mass of zirconium and the molar mass of zirconium when the nuclear fuel cladding in the nuclear containment shell is subjected to oxidation reaction; obtaining the hydrogen species mass within the nuclear fuel cladding based on the zirconium fraction, zirconium mass, zirconium molar mass, and the shell exhaust fraction; obtaining a first steam pressure value, a first hydrogen pressure value and a first air pressure value, wherein the first steam pressure value is determined based on the preset shell temperature value, the shell internal pressure value, the first hydrogen pressure value is determined based on the containment free volume, the preset shell temperature value and the hydrogen content, and the first air pressure value is determined based on the air content in the nuclear containment, the preset shell temperature value and the containment free volume; and when the relation between the pressure sum value and the in-shell pressure value meets a first preset relation, obtaining the hydrogen share in the nuclear containment shell based on the first hydrogen pressure value and the in-shell pressure value, wherein the pressure sum value is the sum of the first hydrogen pressure value, the first air pressure value and the first steam pressure value.

In one embodiment, the fitting relation determining module is used for obtaining a shell initial air pressure value based on the shell initial temperature value and the shell initial pressure value; obtaining an air mass in a nuclear containment vessel based on the shell initial air pressure value, the shell free volume, the ideal gas constant, and the shell exhaust fraction; obtaining a second steam pressure value, a second air pressure value, and a second hydrogen pressure value, the second steam pressure value being determined based on the preset shell temperature value, the shell internal pressure value, the second air pressure value being determined based on the amount of air in the nuclear containment shell, the preset shell temperature value, and the shell free volume, the second hydrogen pressure value being determined based on the shell internal pressure value, the second air pressure value, and the second steam pressure value; and when the relation among the second hydrogen pressure value, the in-shell pressure value and the second steam pressure value meets a second preset relation, determining a hydrogen combustion limit fitting relation between the in-shell pressure value and the hydrogen share based on the second hydrogen pressure value and the in-shell pressure value.

The fitting relation determining module is used for obtaining a nuclear containment failure allowance based on the shell failure probability; obtaining a shell initial air pressure value based on the shell initial temperature value and the shell initial pressure value; obtaining an air mass in the nuclear containment vessel based on the shell initial air pressure value, the shell free volume, the ideal gas constant, and the shell exhaust fraction; obtaining a third vapor pressure value, a third air pressure value, and a third hydrogen pressure value, and a total pre-combustion gas mass, wherein the third vapor pressure value is determined based on the preset shell temperature value, the shell internal pressure value, the third air pressure value is determined based on the air mass in the nuclear containment shell, the preset shell temperature value, and the shell free volume, the third hydrogen pressure value is determined based on the shell internal pressure value, the third air pressure value, and the third vapor pressure value, and the total pre-combustion gas mass is determined based on the shell internal pressure value, the shell free volume, and the preset shell temperature value; obtaining a pre-combustion hydrogen mass and a pre-combustion steam mass, the pre-combustion hydrogen mass being determined based on the pre-combustion gas total mass, the in-shell pressure value, and the third hydrogen pressure value, the pre-combustion steam mass being obtained based on the pre-combustion gas total mass, the in-shell pressure value, and the third steam pressure value; acquiring total mass of combusted gas, steam absorption energy and air absorption energy, wherein the total mass of combusted gas is obtained based on the total mass of combusted hydrogen and the total mass of combusted gas; the steam absorption energy is obtained based on the pre-combustion steam mass, the pre-combustion hydrogen mass, and the specific heat capacity of water; air absorption energy is obtained based on the shell air mass, the pre-combustion hydrogen mass, and the specific heat capacity of air; and when the relation among the nuclear containment failure allowance, the total gas mass before combustion, the total gas mass after combustion, the preset shell temperature value, the hydrogen mass before combustion, the steam absorption energy, the air absorption energy and the preset shell temperature value meets a third preset relation, determining a nuclear containment serious threat fitting relation between the in-shell pressure value and the hydrogen share based on the third hydrogen pressure value and the in-shell pressure value.

In one embodiment, the fitting relation determining module is further configured to determine, according to the preset shell temperature value and the preset shell temperature value reset when the preset shell temperature value determining module does not satisfy the first predetermined relation, and the fitting relation between the preset shell temperature value and the hydrogen share, and further configured to determine, according to the preset shell temperature value determining module and the preset shell temperature value reset when the preset shell temperature value determining module does not satisfy the second predetermined relation, and the fitting relation between the preset shell temperature value and the hydrogen share, and further configured to determine, according to the preset shell temperature value reset when the preset shell temperature value determining module does not satisfy the third predetermined relation, the fitting relation between the preset shell temperature value reset, the preset shell pressure value, the running state parameter, and the system configuration parameter.

For specific limitations of the nuclear containment risk assessment device, reference may be made to the above limitations of the nuclear containment risk assessment method, and no further description is given here. The above-mentioned each module in the nuclear containment risk judging device may be implemented in whole or in part by software, hardware, and a combination thereof. The above modules may be embedded in hardware or independent of a processor in the electronic device, or may be stored in software in a memory in the electronic device, so that the processor may call and execute operations corresponding to the above modules.

In one embodiment, an electronic device is provided, which may be a server, and the internal structure of which may be as shown in fig. 6. The electronic device includes a processor, a memory, and a network interface connected by a system bus. Wherein the processor of the electronic device is configured to provide computing and control capabilities. The memory of the electronic device includes a nonvolatile storage medium and an internal memory. The non-volatile storage medium stores an operating system, computer programs, and a database. The internal memory provides an environment for the operation of the operating system and computer programs in the non-volatile storage media. The database of the electronic device is used to store the in-shell pressure value and the hydrogen fraction in the nuclear containment. The network interface of the electronic device is used for communicating with an external terminal through a network connection. The computer program, when executed by a processor, implements a method for determining risk of a nuclear containment.

In one embodiment, an electronic device is provided, which may be a terminal, and an internal structure diagram thereof may be as shown in fig. 6. The electronic device includes a processor, a memory, a communication interface, a display screen, and an input device connected by a system bus. Wherein the processor of the electronic device is configured to provide computing and control capabilities. The memory of the electronic device includes a nonvolatile storage medium and an internal memory. The non-volatile storage medium stores an operating system and a computer program. The internal memory provides an environment for the operation of the operating system and computer programs in the non-volatile storage media. The communication interface of the electronic device is used for carrying out wired or wireless communication with an external terminal, and the wireless mode can be realized through WIFI, an operator network, NFC (near field communication) or other technologies. The computer program, when executed by a processor, implements a method for determining risk of a nuclear containment. The display screen of the electronic equipment can be a liquid crystal display screen or an electronic ink display screen, and the input device of the electronic equipment can be a touch layer covered on the display screen, can also be keys, a track ball or a touch pad arranged on the shell of the electronic equipment, and can also be an external keyboard, a touch pad or a mouse and the like.

It will be appreciated by those skilled in the art that the structures shown in fig. 6 and 7 are merely block diagrams of portions of structures related to the aspects of the present application and are not intended to limit the electronic device to which the aspects of the present application may be applied, and that a particular electronic device may include more or fewer components than shown, or may combine certain components, or may have different arrangements of components.

In one embodiment, an electronic device is provided that includes a memory having a computer program stored therein and a processor that when executing the computer program performs the steps of the methods described above.

In one embodiment, a computer-readable storage medium is provided, on which a computer program is stored which, when executed by a processor, implements the steps of the methods described above.

Those skilled in the art will appreciate that implementing all or part of the above described methods may be accomplished by way of a computer program stored on a non-transitory computer readable storage medium, which when executed, may comprise the steps of the embodiments of the methods described above. Any reference to memory, storage, database, or other medium used in embodiments provided herein may include at least one of non-volatile and volatile memory. The nonvolatile Memory may include Read-Only Memory (ROM), magnetic tape, floppy disk, flash Memory, optical Memory, or the like. Volatile memory can include random access memory (Random Access Memory, RAM) or external cache memory. By way of illustration, and not limitation, RAM can be in the form of a variety of forms, such as static random access memory (Static Random Access Memory, SRAM) or dynamic random access memory (Dynamic Random Access Memory, DRAM), and the like.

The technical features of the above embodiments may be arbitrarily combined, and all possible combinations of the technical features in the above embodiments are not described for brevity of description, however, as long as there is no contradiction between the combinations of the technical features, they should be considered as the scope of the description.

The above examples merely represent a few embodiments of the present application, which are described in more detail and are not to be construed as limiting the scope of the invention. It should be noted that it would be apparent to those skilled in the art that various modifications and improvements could be made without departing from the spirit of the present application, which would be within the scope of the present application. Accordingly, the scope of protection of the present application is to be determined by the claims appended hereto.

Claims

1. A method for judging risk of a nuclear containment, the method comprising:

acquiring a pressure value in the shell;

obtaining the hydrogen share in the nuclear containment;

Acquiring an operation state parameter and a system configuration parameter of the nuclear containment, wherein the operation state parameter is a parameter for representing the operation state of the nuclear containment, and the system configuration parameter is a parameter for representing the factory configuration of the nuclear containment; the operating state parameters comprise a shell initial temperature value and a shell initial pressure value; the system configuration parameters comprise shell exhaust share, shell free volume and shell failure probability;

based on a preset shell temperature value, the shell internal pressure value, an operating state parameter and a system configuration parameter, determining a fitting relation between the shell internal pressure value and the hydrogen share, wherein the fitting relation between the shell internal pressure value and the hydrogen share comprises the following steps: fitting relation between the in-shell pressure value and hydrogen combustion limit value of hydrogen share, and fitting relation between the in-shell pressure value and nuclear containment of hydrogen share;

and when the pressure value and the hydrogen share meet the fitting relation between the pressure value and the hydrogen share in the shell, determining that the nuclear containment shell is at risk of damage, including:

when the hydrogen share under the pressure value in the shell is in the range of an intersection point formed by the intersection point of the hydrogen combustion limit fitting relation and the nuclear containment serious threat fitting relation of the hydrogen share, determining that the nuclear containment is at risk of damage;

Wherein, based on the preset shell temperature value, the shell internal pressure value, the running state parameter and the system configuration parameter, the fitting relation between the shell internal pressure value and the hydrogen share is determined, comprising:

determining a hydrogen pressure value based on the preset shell temperature value, the shell internal pressure value, the air mass, the shell free volume and the shell internal pressure value;

when the hydrogen content in the shell reaches the combustion limit value, determining a fitting relation between the hydrogen content and the hydrogen combustion limit value of the hydrogen content based on the hydrogen pressure value and the shell internal pressure value;

and when the structure of the nuclear containment shell reaches a damage condition, determining a nuclear containment serious threat fitting relation between the in-shell pressure value and the hydrogen share based on the hydrogen pressure value and the in-shell pressure value.

2. The method according to claim 1, wherein the determining of the preset shell temperature value comprises:

3. The method of claim 1, wherein the system configuration parameters include shell off-gas fraction, shell free volume, shell failure probability, the deriving hydrogen fraction within the containment vessel comprising:

4. A method according to claim 3, further comprising:

5. The method of claim 4, wherein resetting the preset shell temperature value comprises:

6. A method according to claim 3, wherein the operating state parameters include a shell initial temperature value, a shell initial pressure value, and the determination of the air mass comprises:

7. The method of claim 1, wherein the hydrogen pressure value comprises a second hydrogen pressure value; when the hydrogen content in the shell reaches the combustion limit value, determining a hydrogen combustion limit value fitting relation between the hydrogen content and the internal shell pressure value based on the hydrogen pressure value and the internal shell pressure value, wherein the method comprises the following steps:

8. The method as recited in claim 7, further comprising:

9. The method of claim 8, wherein resetting the preset shell temperature value when the relationship between the second hydrogen pressure value, the in-shell pressure value, and the second vapor pressure value does not satisfy the second predetermined relationship comprises:

determining a hydrogen fraction based on the second hydrogen pressure value;

10. The method of claim 9, wherein resetting the preset shell temperature value comprises:

Otherwise, selecting a value larger than the preset shell temperature value of the fourth preset proportion, and resetting the value as the preset shell temperature value.

11. The method of claim 1, wherein the operating state parameters comprise a shell initial temperature value, a shell initial pressure value, the system configuration parameters comprise a shell exhaust fraction, a shell free volume, a shell failure probability, and the hydrogen pressure value comprises a third hydrogen pressure value; when the structure of the nuclear containment shell reaches a damage condition, determining a nuclear containment severe threat fitting relationship between the in-shell pressure value and the hydrogen share based on the hydrogen pressure value and the in-shell pressure value, including:

12. The method as recited in claim 11, further comprising:

13. The method of claim 12, wherein resetting the preset shell temperature value when the relationship between the nuclear containment failure margin, the pre-combustion gas total mass, the post-combustion gas total mass, the preset shell temperature value, the pre-combustion hydrogen mass, the steam absorption energy, the air absorption energy, the preset shell temperature value does not satisfy a third predetermined relationship comprises:

14. The method of claim 13, wherein resetting the preset shell temperature value comprises:

15. A nuclear containment risk judgment apparatus, the apparatus comprising:

The fitting relation determining module is used for obtaining the running state parameters and the system configuration parameters of the nuclear containment, wherein the running state parameters are parameters used for representing the initial state of the nuclear containment, the system configuration parameters are parameters used for representing the factory configuration of the nuclear containment, and the running state parameters comprise a shell initial temperature value and a shell initial pressure value; the system configuration parameters comprise shell exhaust share, shell free volume and shell failure probability; based on a preset shell temperature value, the shell internal pressure value, an operating state parameter and a system configuration parameter, determining a fitting relation between the shell internal pressure value and the hydrogen share, wherein the fitting relation between the shell internal pressure value and the hydrogen share comprises the following steps: fitting relation between the in-shell pressure value and hydrogen combustion limit value of hydrogen share, and fitting relation between the in-shell pressure value and nuclear containment of hydrogen share;

the nuclear containment shell damage risk judging module is further used for determining that the nuclear containment shell has damage risk when the hydrogen share under the pressure value in the shell is in an intersection range formed by an intersection of a hydrogen combustion limit fitting relation and a nuclear containment serious threat fitting relation of the hydrogen share;

16. An electronic device comprising a memory and a processor, the memory storing a computer program, characterized in that the processor implements the steps of the method of any one of claims 1 to 14 when the computer program is executed.

17. A computer readable storage medium, on which a computer program is stored, characterized in that the computer program, when being executed by a processor, implements the steps of the method of any of claims 1 to 14.