CN114091310A - Multi-scale multi-physical field coupling analysis method for package behavior in severe reactor accident - Google Patents
Multi-scale multi-physical field coupling analysis method for package behavior in severe reactor accident Download PDFInfo
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Abstract
The invention discloses a multiscale multi-physical field coupling analysis method for a cladding behavior in a severe accident of a reactor, which comprises the following steps: 1. establishing calculation models under different scales; 2. developing a coupling interface module to realize data transmission among models; 3. calculating a steady-state operation condition and defining an initial condition by nuclear reactor system analysis software; 4. the nuclear reactor system analysis software starts transient accident process simulation; 5. after the state parameters of the lower grid plate are obtained, calling a coupling interface module 1 to transmit data; 6. respectively carrying out calculation by adopting Fluent, Abaqus and a one-dimensional cladding oxidation model; 7. if the calculation results in the step 6 are converged, calling the coupling interface module 1, and continuing to operate the nuclear reactor system analysis software, otherwise calling the coupling interface module 2, and repeating the steps 6 and 7; 8: and if the calculation time is greater than the termination time, terminating the calculation. Otherwise, calculating the next time step and repeating the steps 5-8. The method has important significance for predicting and analyzing the process of the serious accident.
Description
Technical Field
The invention relates to the field of nuclear reactor safety analysis methods, in particular to a multiscale multi-physical field coupling analysis method for a cladding behavior in a severe accident of a reactor.
Background
In a severe accident of a nuclear reactor, the cladding temperature rises rapidly. Under the action of factors such as air gap internal pressure and fuel pellet deformation and extrusion, the cladding generates bulging deformation in the process, the area of a coolant flow passage is reduced, and heat transfer is further deteriorated. With the further increase of the temperature of the cladding, the severe oxidation reaction of the cladding and water vapor occurs, the temperature of the reactor core is accelerated by the chemical heat released in the process, and meanwhile, a brittle oxide phase is generated, so that the mechanical property of the cladding is reduced. When the cladding stress reaches the intensity limit, the cladding will burst, causing the radioactive fission products to escape. Therefore, cladding behavior in a severe accident of the nuclear reactor has great influence on the subsequent accident process, and accurate simulation of the process has great significance for accident prediction and mitigation measure formulation.
The existing nuclear reactor severe accident simulation software generally adopts equivalent node division for a whole reactor core, and simplifies cladding behavior analysis in severe accidents by adopting a cladding oxidation dynamic relation and a failure criterion obtained by experiments based on a quasi-steady state hypothesis. The method cannot consider the coupling effect of the phenomena of cladding deformation, flow channel blockage, oxidation phase change, chemical reaction heat release and the like, and needs to modify a large number of empirical coefficients in a model to achieve an expected simulation result, so that the method is not strong in universality. At present, no relevant reports are found to provide a reasonable scheme for solving the problem, so that the development of a multiscale multi-physical field coupling analysis method for the cladding behavior in the severe accident of the reactor has important significance for predicting and analyzing the process of the severe accident.
Disclosure of Invention
In order to solve the problems in the prior art, the invention aims to provide a multiscale multi-physical field coupling analysis method for the cladding behavior in a severe accident of a reactor, which is used for carrying out high-fidelity refined numerical simulation analysis on the cladding behavior in the severe accident of the reactor.
In order to achieve the purpose, the invention adopts the following technical scheme:
a multiscale multi-physical field coupling analysis method for a cladding behavior in a severe accident of a reactor comprises the following steps:
step 1: respectively establishing calculation models with different scales, which specifically comprises the following contents:
1) establishing a nuclear reactor primary circuit model, a nuclear reactor secondary circuit model and a containment system model by adopting nuclear reactor system analysis software;
2) respectively establishing a geometric model and a grid model of the full-size fuel assembly of the full reactor core by adopting computational fluid dynamics software Fluent and finite element analysis software Abaqus;
3) selecting a plurality of heights at equal intervals along the axial direction of each fuel rod, selecting a plurality of positions at equal angles along the circumferential direction of each height, and finally performing fine grid division along the cladding radial direction to establish a one-dimensional cladding oxidation model, wherein the model comprises the following contents:
oxygen atom diffusion model:
in the formula: cOIs the oxygen atom concentration, D is the oxygen atom diffusion coefficient, r is the space coordinate, and t is the time;
II, phase interface migration model:
in the formula: p and p-1 are the numbers of two adjacent phases, CO,pIs p phase at phase interfaceOxygen atom concentration of CO,p-1Is the oxygen atom concentration of the p-1 phase at the phase interface, and xi is the position of the phase interface;
III, chemical reaction thermal model: q · Δ F, wherein: q is the heat flux density of the chemical reaction heat, Q is the heat released by zirconium atoms and oxygen atoms combined to generate zirconium dioxide in unit substance amount, and delta F is the oxygen atom flux density difference between different phases at the phase interface;
step 2: a coupling interface module 1 of nuclear reactor system analysis software and computational fluid dynamics software Fluent is developed by adopting a dynamic link library; a coupling interface module 2 of a Fluent model, an Abaqus model and a one-dimensional cladding oxidation model is developed by adopting a multi-physical field coupling tool MPCCI and user-defined functions of a computational fluid dynamics software Fluent and a finite element analysis software Abaqus;
the coupling interface module 1 specifically includes the following:
1) the nuclear reactor system analysis software provides temperature, speed and pressure parameter distribution at a grid plate under a reactor core to the Fluent model to serve as an inlet boundary condition of the Fluent model;
2) the Fluent model provides the temperature, speed and pressure parameter distribution at an outlet to nuclear reactor system analysis software to serve as state parameters of a grid plate on a reactor core;
the coupling interface module 2 specifically includes the following contents:
1) the Fluent model can obtain the temperature distribution of the whole reactor core; the one-dimensional cladding oxidation model updates the cladding radial temperature distribution at each selected position according to the temperature distribution of the whole reactor core; the Abaqus model updates the temperature distribution of the reactor core according to the temperature distribution of the whole reactor core, calculates the cladding internal pressure of each fuel rod according to an ideal gas state equation, and updates the distribution load of the inner surface of the cladding;
2) the Abaqus model can obtain node coordinates and displacement of the whole reactor core cladding, and the one-dimensional cladding oxidation model updates the cladding geometric dimension at each selected position according to the node coordinates and displacement of the whole reactor core cladding; the Fluent model updates the boundaries of the fluid domain and the solid domain according to the node coordinates and the displacement of the whole reactor core cladding, and then optimizes the grid arrangement of the calculation domain through the self-adaptive grid;
3) the one-dimensional cladding oxidation model can obtain the oxygen atom concentration and the chemical reaction heat source distribution at each selected position, and the Fluent model updates the cladding physical property and the heat conduction equation source items at each position of the reactor core by adopting an interpolation method and combining the reactor core temperature distribution according to the oxygen atom concentration and the chemical reaction heat source distribution at each selected position; the Abaqus model updates the physical properties of cladding at each part of the reactor core by adopting an interpolation method according to the oxygen atom concentration and the chemical reaction heat source distribution at each selected position and combining the reactor core temperature distribution;
and step 3: defining initial conditions of a nuclear reactor system model, a Fluent model, an Abaqus model and a one-dimensional cladding oxidation model, and specifically comprising the following contents:
1) adopting nuclear reactor system analysis software to obtain the reactor state under the steady-state operation condition;
2) according to the reactor core state under the steady state, defining initial temperature and speed parameter fields in a Fluent model, defining an initial temperature field in an Abaqus model, and defining radial temperature distribution of each selected position of a one-dimensional cladding oxidation model;
3) the initial strain of each fuel rod cladding in the Abaqus model is 0, the internal pressure is a calculated value of nuclear reactor system analysis software, and two ends of each fuel rod cladding are set as fixed constraints;
4) the initial oxygen atom concentration of each selected position of the one-dimensional cladding oxidation model is 0;
5) the Fluent model and the Abaqus model calculate the initial cladding physical properties of all parts of the reactor core according to the initial oxygen atom concentration in the step 4) by adopting an interpolation method and combining a reactor core temperature field;
and 4, step 4: defining an accident type and a safety system starting logic in nuclear reactor system analysis software, and starting transient process simulation;
and 5: when the nuclear reactor system analysis software calculates and obtains the temperature, speed and pressure parameter distribution at the grid plate under the reactor core, the operation is suspended, the coupling interface module 1 is called, and relevant parameters are transmitted to the Fluent model;
step 6: calculating to obtain reactor core temperature, speed and pressure parameter distribution by adopting a Fluent model, calculating to obtain the stress strain state of each fuel rod cladding by adopting an Abaqus model, and calculating to obtain the oxygen atom concentration and chemical reaction heat source distribution at each selected position by adopting a one-dimensional cladding oxidation model;
and 7: if the reactor core temperature, the speed and the pressure parameter distribution calculated by the Fluent model, the stress strain state of each fuel rod cladding calculated by the Abaqus model, the oxygen atom concentration at each selected position calculated by the one-dimensional cladding oxidation model and the relative error between the chemical reaction heat source distribution and the last iteration calculation result are smaller than a set value, calling the coupling interface module 1, transmitting the temperature, the speed, the pressure and other parameter distributions at the outlet of the Fluent model to the nuclear reactor system analysis software, continuously operating the nuclear reactor system analysis software, completing the subsequent calculation within the current time step, and then executing the step 8; otherwise, calling the coupling interface module 2, and repeating the step 6 and the step 7;
and 8: if the calculation time is longer than the set termination time, terminating the calculation; otherwise, calculating the next time step, and repeating the steps 5-8.
Compared with the prior art, the invention has the following advantages:
1. the method can realize multi-scale coupling calculation of diffusion of nuclear power plant systems, fuel rods and mesoscopic atoms, and can be used for mechanism research of cladding behaviors in severe accidents of nuclear reactors.
2. The method can realize multi-physical field coupling calculation of heat transfer, mass transfer and mechanical characteristics, and can be used for high-fidelity refined cladding behavior simulation in severe accidents of nuclear reactors.
3. Compared with the traditional nuclear reactor severe accident simulation software, the method greatly reduces the empirical relations in the reactor core model, and obviously improves the universality.
And 4, judging whether the cladding failure occurs or not by the Abaqus model based on a mechanical strength theory, and improving the prediction precision of the cladding failure behavior.
Drawings
FIG. 1 is a calculation flow chart of a multiscale multi-physics coupling analysis method for the incrustation behavior in a severe accident of a reactor.
Fig. 2 is a schematic data transmission diagram of a coupling interface module 1 of a multiscale multi-physical field coupling analysis method of a cladding behavior in a severe accident of a reactor.
Fig. 3 is a schematic data transmission diagram of a coupling interface module 2 of a multiscale multi-physical field coupling analysis method of a cladding behavior in a severe accident of a reactor.
Detailed Description
The invention is described in detail below with reference to the following figures and detailed description:
as shown in fig. 1, the multi-scale multi-physical field coupling analysis method for the incrustation behavior in a severe accident of a reactor, provided by the invention, comprises the following steps:
step 1: respectively establishing calculation models with different scales, wherein the calculation models specifically comprise the following contents:
1) and (3) adopting nuclear reactor system analysis software to establish a primary loop, a secondary loop and a containment system model of the reactor, and realizing the modeling of the system scale of the nuclear power plant.
2) And respectively establishing a geometric model and a grid model of the full-size fuel assembly of the full reactor core by adopting computational fluid dynamics software Fluent and finite element analysis software Abaqus to realize the modeling of the fuel rod dimension.
3) And selecting a plurality of heights at equal intervals along the axial direction of each fuel rod, selecting a plurality of positions at equal angles along the circumferential direction of each height, and finally performing fine grid division along the cladding radial direction to establish a one-dimensional cladding oxidation model so as to realize mesoscopic scale modeling. The model comprises the following contents:
oxygen atom diffusion model:
in the formula: cOIs the oxygen atom concentration, D is the oxygen atom diffusion coefficient, r is the spatial coordinate, and t is time.
II, phase interface migration model:
in the formula: p and p-1 are the numbers of two adjacent phases, CO,pAs oxygen source of p-phase at phase interfaceSub concentration, CO,p-1Is the oxygen atom concentration of the p-1 phase at the phase interface, and xi is the phase interface position.
III, chemical reaction thermal model: q · Δ F, wherein: q is the heat flux density of the heat of the chemical reaction, Q is the amount of heat released by the zirconium atoms combined with the oxygen atoms to form zirconium dioxide per unit mass, and Δ F is the difference in flux density of oxygen atoms between different phases at the phase interface.
Step 2: a coupling interface module 1 of nuclear reactor system analysis software and computational fluid dynamics software Fluent is developed by adopting a dynamic link library; and developing a coupling interface module 2 of a Fluent model, an Abaqus model and a one-dimensional cladding oxidation model by adopting a multi-physical field coupling tool MPCCI and user-defined functions of a computational fluid dynamics software Fluent and a finite element analysis software Abaqus.
As shown in fig. 2, the coupling interface module 1 specifically includes the following contents:
1) and (3) providing parameter distribution such as temperature, speed, pressure and the like at a grid plate under the reactor core for the Fluent model by the nuclear reactor system analysis software, and taking the parameter distribution as an import boundary condition of the Fluent model.
2) The Fluent model provides the parameter distribution of temperature, speed, pressure and the like at an outlet to nuclear reactor system analysis software as state parameters of a grid plate on a reactor core.
As shown in fig. 3, the coupling interface module 2 specifically includes the following contents:
1) the Fluent model can obtain the temperature distribution of the whole core. The one-dimensional cladding oxidation model updates the cladding radial temperature distribution at each selected position according to the temperature distribution of the whole reactor core; the Abaqus model updates the temperature distribution of the reactor core according to the temperature distribution of the whole reactor core, calculates the cladding internal pressure of each fuel rod according to an ideal gas state equation, and updates the distribution load of the inner surface of the cladding.
2) The Abaqus model can obtain the node coordinates and displacements of the total core clad. Updating the cladding geometric dimensions of each selected position by the one-dimensional cladding oxidation model according to the node coordinates and the displacement of the full reactor core cladding; and the Fluent model updates the boundary of the fluid domain and the solid domain according to the node coordinates and the displacement of the whole reactor core cladding, and then optimizes the grid arrangement of the calculation domain through the self-adaptive grid.
3) The one-dimensional wrapper oxidation model can obtain the oxygen atom concentration and the chemical reaction heat source distribution at each selected position. The Fluent model updates the physical properties of cladding and the source items of a heat conduction equation at each position of the reactor core by adopting an interpolation method and combining the temperature distribution of the reactor core according to the oxygen atom concentration and the chemical reaction heat source distribution at each selected position; and updating the physical properties of cladding at each part of the reactor core by adopting an interpolation method according to the oxygen atom concentration and the chemical reaction heat source distribution at each selected position and combining the reactor core temperature distribution by using the Abaqus model.
And step 3: initial conditions of a nuclear reactor system model, a Fluent model, an Abaqus model, and a one-dimensional cladding oxidation model are defined. The method specifically comprises the following steps:
1) and (4) adopting nuclear reactor system analysis software to obtain the reactor state under the steady-state operation working condition.
2) According to the reactor core state under the steady state, parameter fields such as initial temperature, speed and the like in the Fluent model are defined, an initial temperature field in the Abaqus model is defined, and radial temperature distribution of each selected position of the one-dimensional cladding oxidation model is defined.
3) The initial strain of each fuel rod cladding in the Abaqus model was 0, the internal pressure was calculated by the nuclear reactor system analysis software, and the two ends of each fuel rod cladding were set as fixed constraints.
4) The initial oxygen atom concentration of each selected position of the one-dimensional cladding oxidation model is 0.
5) The Fluent model and the Abaqus model calculate the initial cladding physical properties of all parts of the reactor core according to the initial oxygen atom concentration in the step 4) by adopting an interpolation method and combining a reactor core temperature field.
And 4, step 4: defining accident type and safety system starting logic in the nuclear reactor system analysis software, and starting transient process simulation.
And 5: when the nuclear reactor system analysis software calculates and obtains the distribution of parameters such as temperature, speed, pressure and the like at a grid plate under a reactor core, the operation is suspended, the coupling interface module 1 is called, and relevant parameters are transmitted to the Fluent model.
And 6: the reactor core temperature, speed, pressure and other parameter distributions are calculated and obtained by adopting a Fluent model, the stress-strain state of each fuel rod cladding is calculated and obtained by adopting an Abaqus model, and the oxygen atom concentration and the chemical reaction heat source distribution at each selected position are calculated and obtained by adopting a one-dimensional cladding oxidation model.
And 7: if the reactor core temperature, the speed and the pressure parameter distribution calculated by the Fluent model, the stress strain state of each fuel rod cladding calculated by the Abaqus model, the oxygen atom concentration at each selected position calculated by the one-dimensional cladding oxidation model, and the relative error between the chemical reaction heat source distribution and the last iteration calculation result are smaller than set values, calling the coupling interface module 1, transmitting the temperature, the speed, the pressure and other parameter distributions at the outlet of the Fluent model to nuclear reactor system analysis software, continuously operating the nuclear reactor system analysis software, completing the subsequent calculation within the time step, and then executing the step 8; otherwise, calling the coupling interface module 2 and repeating the step 6 and the step 7.
And 8: and if the calculation time is greater than the set termination time, terminating the calculation. Otherwise, calculating the next time step and repeating the steps 5-8.
While the invention has been described in further detail with reference to specific preferred embodiments thereof, it will be understood by those skilled in the art that various changes in form and details may be made therein without departing from the spirit and scope of the invention as defined by the appended claims.
Claims (1)
1. A multiscale multi-physical field coupling analysis method for a cladding behavior in a severe accident of a reactor is characterized by comprising the following steps: the method comprises the following steps:
step 1: respectively establishing calculation models with different scales, wherein the calculation models specifically comprise the following contents:
1) establishing a nuclear reactor primary circuit model, a nuclear reactor secondary circuit model and a containment system model by adopting nuclear reactor system analysis software;
2) respectively establishing a geometric model and a grid model of the full-size fuel assembly of the full reactor core by adopting computational fluid dynamics software Fluent and finite element analysis software Abaqus;
3) selecting a plurality of heights at equal intervals along the axial direction of each fuel rod, selecting a plurality of positions at equal angles along the circumferential direction of each height, and finally performing fine grid division along the cladding radial direction to establish a one-dimensional cladding oxidation model, wherein the model comprises the following contents:
oxygen atom diffusion model:
in the formula: cOIs the oxygen atom concentration, D is the oxygen atom diffusion coefficient, r is the space coordinate, and t is the time;
II, phase interface migration model:
in the formula: p and p-1 are the numbers of two adjacent phases, CO,pIs the oxygen atom concentration of the p-phase at the phase interface, CO,p-1Is the oxygen atom concentration of the p-1 phase at the phase interface, and xi is the position of the phase interface;
III, chemical reaction thermal model: q · Δ F, wherein: q is the heat flux density of the chemical reaction heat, Q is the heat released by the zirconium atoms combined with the oxygen atoms to generate zirconium dioxide in unit mass amount, and delta F is the oxygen atom flux density difference between different phases at the phase interface;
and 2, step: a coupling interface module 1 of nuclear reactor system analysis software and computational fluid dynamics software Fluent is developed by adopting a dynamic link library; a coupling interface module 2 of a Fluent model, an Abaqus model and a one-dimensional cladding oxidation model is developed by adopting a multi-physical field coupling tool MPCCI and user-defined functions of a computational fluid dynamics software Fluent and a finite element analysis software Abaqus;
the coupling interface module 1 specifically includes the following:
1) the nuclear reactor system analysis software provides temperature, speed and pressure parameter distribution at a grid plate under a reactor core to the Fluent model to serve as an inlet boundary condition of the Fluent model;
2) the Fluent model provides the temperature, speed and pressure parameter distribution at an outlet to nuclear reactor system analysis software to serve as state parameters of a grid plate on a reactor core;
the coupling interface module 2 specifically includes the following contents:
1) the Fluent model can obtain the temperature distribution of the whole reactor core; the one-dimensional cladding oxidation model updates the cladding radial temperature distribution at each selected position according to the temperature distribution of the whole reactor core; the Abaqus model updates the temperature distribution of the reactor core according to the temperature distribution of the whole reactor core, calculates the cladding internal pressure of each fuel rod according to an ideal gas state equation and updates the distribution load of the inner surface of the cladding;
2) the Abaqus model can obtain node coordinates and displacement of the whole reactor core cladding, and the one-dimensional cladding oxidation model updates the cladding geometric dimensions at each selected position according to the node coordinates and displacement of the whole reactor core cladding; the Fluent model updates the boundaries of the fluid domain and the solid domain according to the node coordinates and the displacement of the whole reactor core cladding, and then optimizes the grid arrangement of the calculation domain through the self-adaptive grid;
3) the one-dimensional cladding oxidation model can obtain the oxygen atom concentration and the chemical reaction heat source distribution at each selected position, and the Fluent model updates the cladding physical property and the heat conduction equation source items at each position of the reactor core by adopting an interpolation method and combining the reactor core temperature distribution according to the oxygen atom concentration and the chemical reaction heat source distribution at each selected position; the Abaqus model updates the physical properties of cladding at each position of the reactor core by adopting an interpolation method and combining the temperature distribution of the reactor core according to the oxygen atom concentration and the chemical reaction heat source distribution at each selected position;
and step 3: defining initial conditions of a nuclear reactor system model, a Fluent model, an Abaqus model and a one-dimensional cladding oxidation model, and specifically comprising the following contents:
1) adopting nuclear reactor system analysis software to obtain the reactor state under the steady-state operation condition;
2) according to the reactor core state under the steady state, defining initial temperature and speed parameter fields in a Fluent model, defining an initial temperature field in an Abaqus model, and defining radial temperature distribution of each selected position of a one-dimensional cladding oxidation model;
3) the initial strain of each fuel rod cladding in the Abaqus model is 0, the internal pressure is a calculated value of nuclear reactor system analysis software, and two ends of each fuel rod cladding are set as fixed constraints;
4) the initial oxygen atom concentration of each selected position of the one-dimensional cladding oxidation model is 0;
5) the Fluent model and the Abaqus model calculate the initial cladding physical properties of all parts of the reactor core according to the initial oxygen atom concentration in the step 4) by adopting an interpolation method and combining a reactor core temperature field;
and 4, step 4: defining accident type and safety system starting logic in nuclear reactor system analysis software, and starting transient process simulation;
and 5: when the nuclear reactor system analysis software calculates and obtains the temperature, speed and pressure parameter distribution at the grid plate under the reactor core, the operation is suspended, the coupling interface module 1 is called, and relevant parameters are transmitted to the Fluent model;
step 6: calculating to obtain reactor core temperature, speed and pressure parameter distribution by adopting a Fluent model, calculating to obtain the stress strain state of each fuel rod cladding by adopting an Abaqus model, and calculating to obtain the oxygen atom concentration and chemical reaction heat source distribution at each selected position by adopting a one-dimensional cladding oxidation model;
and 7: if the reactor core temperature, the speed and the pressure parameter distribution calculated by the Fluent model, the stress strain state of each fuel rod cladding calculated by the Abaqus model, the oxygen atom concentration at each selected position calculated by the one-dimensional cladding oxidation model and the relative error between the chemical reaction heat source distribution and the last iteration calculation result are smaller than a set value, calling the coupling interface module 1, transmitting the temperature, the speed and the pressure parameter distribution at the outlet of the Fluent model to nuclear reactor system analysis software, continuously operating the nuclear reactor system analysis software, completing the subsequent calculation within the current time step, and then executing the step 8; otherwise, calling the coupling interface module 2, and repeating the step 6 and the step 7;
and step 8: if the calculation time is longer than the set termination time, terminating the calculation; otherwise, calculating the next time step and repeating the steps 5-8.
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| CN110598324A (en) * | 2019-09-12 | 2019-12-20 | 西安交通大学 | Nuclear reactor dispersion plate type fuel element core fluid-solid coupling calculation method |
| CN111291494A (en) * | 2020-02-21 | 2020-06-16 | 西安交通大学 | Multi-scale multi-physical field coupling simulation method for TRISO fuel particles of nuclear reactor |
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| CN114860235A (en) * | 2022-04-14 | 2022-08-05 | 西安交通大学 | Method for coupling commercial software and self-programming software |
| CN114860235B (en) * | 2022-04-14 | 2024-04-09 | 西安交通大学 | Method for coupling commercial software and self-programming software |
| CN115270660A (en) * | 2022-08-04 | 2022-11-01 | 上海交通大学 | Multi-scale multi-physical field coupling analysis method for transient behavior of space thermionic reactor |
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