CN109902433B - Cross-dimension coupling method for pressurized water reactor passive containment waste heat discharge system - Google Patents
Cross-dimension coupling method for pressurized water reactor passive containment waste heat discharge system Download PDFInfo
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Abstract
The invention discloses a cross-dimension coupling method of a pressurized water reactor passive containment waste heat removal system, which comprises the following steps: 1. establishing a passive containment waste heat discharge system model by utilizing a one-dimensional thermal hydraulic calculation analysis program; 2. establishing a containment three-dimensional computational fluid dynamics analysis model, and calculating by using computational fluid dynamics software CFX; 3. completing the exchange of the one-dimensional thermal hydraulic calculation analysis program and computational fluid dynamics software CFX data; 4. and (4) repeating the step (3) until the requirement of calculating time is met. The method can accurately calculate the values of the temperature, the pressure and the steam share in the containment under the action of the passive containment waste heat discharge system, and has important significance on safety analysis after an accident.
Description
Technical Field
The invention belongs to the technical field of nuclear reactor safety analysis, and particularly relates to a cross-dimension coupling analysis method for influence of a passive containment waste heat discharge system on flow field distribution in a containment after an accident.
Background
The containment vessel is the last barrier to prevent radioactive materials in the reactor from leaking out in an accident situation, and therefore the integrity of the containment vessel is critical to the safety of the nuclear reactor. The traditional pressurized water reactor nuclear power plant generally utilizes a containment vessel spraying system to lead out heat inside a containment vessel after a breach accident happens, and the integrity of the containment vessel is prevented from being lost due to overtemperature and overpressure. However, when an over-design basis accident such as a full-field power failure and the like in which an external power supply is lost occurs, the containment vessel spraying system fails due to the loss of the external power supply, so that the integrity of the containment vessel faces a great threat.
at present, the nuclear reactor safety analysis method generally comprises three methods, namely 1, system analysis, such as RE L AP5 program, TRACE program and other one-dimensional system analysis programs, 2, Computational Fluid Dynamics (CFD) simulation, such as ANSYS CFX software and other programs, and 3, subchannel analysis programs, such as COBRA program and other programs, wherein the one-dimensional system analysis programs cannot analyze and calculate complex three-dimensional thermohydraulic phenomena, the CFD method is complex in modeling, long in transient calculation time consumption and incomplete in model, and has great limitation when being used for nuclear reactor safety analysis, and the subchannel analysis method is simple in modeling, low in calculation requirement and also has great limitation on three-dimensional phenomena in an analysis containment.
in the design of an extended working condition, particularly under the condition of a serious accident, the gas in a containment vessel contains air, steam, hydrogen and the like, and the flowing and heat transfer of the gas are three-dimensional phenomena in essence, the thermal environment in the containment vessel under the action of a containment vessel spraying system is relatively uniform and can be well solved by adopting a traditional lumped parameter program, however, the thermal hydraulic phenomena of the containment vessel under the action of a passive system can present the phenomenon of gas layering or thermal layering with uneven local thermal parameter distribution, at the moment, the traditional lumped parameter program cannot be accurately simulated, and the three-dimensional computational fluid mechanics program can be well simulated.
Liu Yu of the Qing university is based on an RE L AP5 program and a CFX program, and is programmed by utilizing a parallel virtual machine technology and a CFX user function, an RE L AP5/CFX coupling program is developed, in a single-phase range, the accuracy of coupling among programs is verified by utilizing a horizontal circular tube blowing problem, then, simulation is carried out on a double-T-shaped connection tube mixing experiment, relative to an independent RE L AP5 program, the coupling program can better reveal real physical phenomena, through subsequent development, the coupling program can be used for solving the problem that a remarkable three-dimensional mixing phenomenon exists in reactor safety analysis, Liu Yu is further subjected to the mutual coupling by researching an internal structure of a subchannel program (COBRA-IV) and a computational fluid mechanics program (CFX), an interface for mutual coupling is developed, the idea of displaying a time iteration mode and area decomposition is adopted, data is exchanged through an external control program, the COBRA-IV/CFX coupling program is established, the coupling between components and local scale in multi-scale coupling simulation is realized, the transient state coupling result and the steady-state coupling calculation accuracy problem is verified by adopting the transient state coupling program for a 5X5 bundle assembly.
in order to better predict and analyze complex thermal hydraulic phenomena in the ultra-high temperature gas cooled reactor under normal working conditions and accident working conditions, Anderson N and the like in the United states couple RE L AP5-3D with CFD software F L UENT, the Anderson N and the like select the thermal mixing phenomenon after coolant in the gas cooled reactor enters an upper cavity from a reactor core, model the ultra-high temperature gas cooled reactor by utilizing RE L AP5-3D, model a local upper cavity by utilizing F L UENT, and provide an inlet boundary condition for F L UENT under the outlet condition of RE L AP 5.
Davide Bertolotto et al, Switzerland coupled the three-dimensional computational fluid dynamics software CFX with the thermal hydraulic optimal estimation program TRACE and performed corresponding validation. The first verified working condition of the coupling procedure is the problem of the discharge of a horizontal round tube filled with fluid; the second step of the validation is to compute for the double-T-takeover mixing problem. The calculation result shows that the three-dimensional simulation result has great advantages compared with the one-dimensional simulation result.
Disclosure of Invention
In order to solve the problems, the invention provides a cross-dimension coupling method of a pressurized water reactor passive containment waste heat removal system. The method can not only calculate various thermal hydraulic phenomena in the passive containment waste heat discharge system, but also accurately calculate the values of temperature, pressure and steam share in the containment under the action of the passive containment waste heat discharge system.
In order to achieve the purpose, the invention adopts the following technical scheme:
A pressurized water reactor passive containment waste heat discharge system cross-dimension coupling method is characterized in that a passive containment waste heat discharge system is modeled through a one-dimensional thermodynamic calculation analysis program aiming at a containment environment after the passive containment waste heat discharge system is put into operation after an accident, modeling analysis is carried out on the interior of a containment and a heat exchanger part of the passive containment waste heat discharge system by adopting three-dimensional computational fluid dynamics (CFX), values of temperature, pressure and steam share in the containment under the action of the passive containment waste heat discharge system are obtained, and one-dimensional to three-dimensional cross-dimension coupling analysis is realized; the method specifically comprises the following steps:
Step 1: according to the structure of the passive containment waste heat discharge system, a passive containment waste heat discharge system model is established through a nuclear power system one-dimensional thermal hydraulic calculation analysis program; the passive containment waste heat discharge system model comprises a heat exchanger calculation model, an ascending section pipeline model, a descending section pipeline model, a heat exchange water tank model and a heat exchange water tank water replenishing model, so that a thermodynamic hydraulic response process of the passive containment waste heat discharge system after the passive containment waste heat discharge system is put into operation is simulated and calculated, key parameters of the wall temperature of a heat exchange pipe of the heat exchanger and the natural circulation flow are obtained, and the passive containment waste heat discharge system models are connected through a flow channel to realize the exchange of mass, momentum and energy among the system models;
Step 2: modeling a containment and a heat exchanger in the containment by using commercial grid generation software ICEM CFD, introducing a geometric model of the containment and the heat exchanger into computational fluid dynamics software CFX, and adding a mass source item and a momentum source item in a control equation of the computational fluid dynamics software CFX to consider mass loss and energy loss caused by steam condensation containing non-condensable gas in a computational domain, so as to realize the computation of the amount of the steam containing the non-condensable gas condensed in the containment by the computational fluid dynamics software CFX;
And step 3: the one-dimensional thermal hydraulic calculation analysis program completes calculation of Tn moment by taking temperature, pressure and steam share in a containment at Tn-1 moment as boundary conditions to obtain the wall temperature of a heat exchange tube of a heat exchanger at Tn moment, computational fluid dynamics (CFX) reads the wall temperature of the heat exchange tube of the heat exchanger calculated by the one-dimensional thermal hydraulic calculation analysis program to serve as the boundary conditions at Tn moment, and after the computational fluid dynamics (CFX) completes calculation of the Tn moment, the one-dimensional thermal hydraulic calculation analysis program reads the temperature, the pressure and the steam share in the containment at Tn moment calculated by the computational fluid dynamics (CFX) and calculates the Tn +1 moment;
And 4, step 4: repeating the step (3) until the required calculation time span is reached; and finally, obtaining the values of the temperature, the pressure and the steam share in the containment after the passive containment waste heat discharge system is put into operation.
The invention has the following advantages and beneficial effects:
1. The defect that only one-dimensional analysis and calculation can be carried out by a system analysis program is overcome, and the three-dimensional calculation of the flow field temperature field in the containment is realized;
2. The method has the capability of simulating the layering phenomenon of the gas in the containment under the action of the passive containment waste heat discharge system, and avoids complex three-dimensional modeling;
3. The passive containment waste heat removal system program is relatively independent of the computational fluid dynamics software CFX, and can be independently operated;
4. The condensation process of the water vapor containing the non-condensable gas near the wall surface of the heat exchanger in the containment can be accurately simulated;
5. The corresponding fluid flow heat transfer phenomenon in the containment after the passive containment waste heat removal system is put into operation under various accident conditions can be calculated;
6. The method has the advantages of less computing resource consumption, high computing speed and high computing result precision.
Practice proves that the method can accurately simulate the three-dimensional thermotechnical hydraulic phenomenon in the containment after the passive containment waste heat discharge system is put into operation.
Drawings
FIG. 1 is a schematic diagram of a passive containment residual heat removal system.
FIG. 2 is a schematic diagram of node division of a passive containment waste heat removal system model.
FIG. 3 is a containment and heat exchanger model.
Fig. 4 shows a coupling method.
The specific implementation mode is as follows:
The invention is described in further detail below with reference to the following figures and detailed description:
The invention provides a cross-dimension coupling method for a pressurized water reactor passive containment waste heat removal system, which comprises the following specific steps:
the method comprises the following steps of 1, establishing a passive containment waste heat discharge system model by adopting any known nuclear power system one-dimensional thermodynamic calculation analysis program such as RE L AP5 program, TRAC program and RETRAN program according to a pressurized water reactor passive containment waste heat discharge system schematic diagram shown in figure 1, wherein the passive containment waste heat discharge system model comprises a heat exchanger calculation model, an ascending section pipeline model, a descending section pipeline model, a heat exchange water tank model and a heat exchange water tank water supplement model, so that a thermodynamic response process of the passive containment waste heat discharge system after the passive containment waste heat discharge system is put into operation is simulated and calculated, and key parameters of heat exchange pipe wall temperature and natural circulation flow of the heat exchanger are obtained.
A schematic node division diagram of the passive containment waste heat removal system model is shown in fig. 2 and includes a heat exchange water tank, a heat exchanger, an ascending section and a descending section pipeline. The model comprises 40 control bodies, wherein 5 control bodies are divided by a heat exchange water tank, 5 control bodies are divided by a descending section 1, 5 control bodies are divided by a section 2, 10 control bodies are divided by a heat exchanger, 10 control bodies are divided by an ascending section 1, and 5 control bodies are divided by an ascending section 2. Then, the flow channel is used for connecting two adjacent control bodies, and the mass transfer, energy transfer and momentum transfer processes between the control bodies (between system devices) are simulated.
Step 2: modeling the containment and the heat exchanger in the containment by using commercial grid generation software ICEM CFD, as shown in FIG. 3, introducing a geometric model of the containment and the heat exchanger into computational fluid dynamics software CFX, and adding a mass source term and a momentum source term in a control equation of the computational fluid dynamics software CFX to consider mass loss and energy loss caused by condensation of steam containing non-condensable gas in a computational domain, so as to realize the computation of the condensation amount of the steam containing the non-condensable gas in the containment by the computational fluid dynamics software CFX;
When the computational fluid dynamics (CFX) software is adopted to calculate the condensation quantity of the steam containing the non-condensable gas in the containment vessel, the two-phase fluid is not considered, and the flow of a condensate film is not considered. Wherein the calculation formula of mass loss when the water vapor condenses is as follows:
In the formula:
Cu-adjusting the coefficients;
A-area of condensation wall/m 2；
T-water vapor temperature/. degree.C.;
TwallWall temperature/° c;
hlgSaturated steam latent heat of vaporization/J.kg -1；
ρgWater vapor density/kg m -3；
ρn-density of non-condensable gas/kg.m -3。
The energy loss of water vapor condensation can be calculated by the following formula:
H0＝m0(Tcp,m-Twallcp,g)
In the formula: m is 0-steam condensation rate/kg · s -1；
cp,mConstant pressure heat capacity/J.kg of mixed gas -1·K-1；
cp,g-constant pressure heat capacity/J.kg of non-condensable gas -1×K-1；
T-water vapor temperature/. degree.C.;
TrefReference temperature at enthalpy 0, 273.15K.
And step 3: as shown in fig. 4, the one-dimensional thermodynamic calculation and analysis program completes the calculation of the Tn time by using the temperature, pressure and steam fraction in the containment at the Tn-1 time as boundary conditions to obtain the wall temperature of the heat exchange tube at the Tn time, the computational fluid dynamics software CFX reads the wall temperature of the heat exchange tube of the heat exchanger calculated by the one-dimensional thermodynamic calculation and analysis program as the boundary conditions at the Tn time, and after the computational fluid dynamics software CFX completes the calculation at the Tn time, the one-dimensional thermodynamic calculation and analysis program reads the temperature, pressure and steam fraction in the containment at the Tn time obtained by the computational fluid dynamics software CFX and performs the calculation at the Tn +1 time;
And 4, step 4: carrying out next time step calculation, and repeating the step (3); until the required calculation time span is reached. And finally, obtaining the values of the temperature, the pressure and the steam share in the containment after the passive containment waste heat discharge system is put into operation.
Claims (1)
1. A cross-dimension coupling method for a pressurized water reactor passive containment waste heat removal system is characterized by comprising the following steps: aiming at the containment environment after the passive containment waste heat discharge system is put into operation after an accident, modeling is carried out on the passive containment waste heat discharge system through a one-dimensional thermodynamic calculation analysis program, and modeling analysis is carried out on the interior of a containment and a heat exchanger part of the passive containment waste heat discharge system through three-dimensional calculation hydrodynamics software CFX, so that the values of temperature, pressure and steam share in the containment under the action of the passive containment waste heat discharge system are obtained, and one-dimensional to three-dimensional cross-dimension coupling analysis is realized;
The cross-dimension coupling method specifically comprises the following steps:
Step 1: according to the structure of the passive containment waste heat discharge system, a passive containment waste heat discharge system model is established through a nuclear power system one-dimensional thermal hydraulic calculation analysis program; the passive containment waste heat discharge system model comprises a heat exchanger calculation model, an ascending section pipeline model, a descending section pipeline model, a heat exchange water tank model and a heat exchange water tank water replenishing model, so that a thermodynamic hydraulic response process of the passive containment waste heat discharge system after the passive containment waste heat discharge system is put into operation is simulated and calculated, key parameters of the wall temperature of a heat exchange pipe of the heat exchanger and the natural circulation flow are obtained, and the passive containment waste heat discharge system models are connected through a flow channel to realize the exchange of mass, momentum and energy among the system models;
Step 2: modeling a containment and a heat exchanger in the containment by using grid generation software ICEM CFD, introducing a geometric model of the containment and the heat exchanger into computational fluid dynamics software CFX, and adding a mass source item and a momentum source item in a control equation of the computational fluid dynamics software CFX to consider mass loss and energy loss caused by condensation of steam containing non-condensable gas in a computational domain, so as to realize the computation of the condensation amount of the steam containing the non-condensable gas in the containment by the computational fluid dynamics software CFX;
And step 3: one-dimensional thermal hydraulic calculation analysis program passes through T n-1The temperature, pressure and steam content in the containment vessel are used as boundary conditions to complete T nCalculating the time to obtain T nAt any moment, the wall temperature of the heat exchange tube of the heat exchanger is read by computational fluid dynamics (CFX) software to obtain the wall temperature of the heat exchange tube of the heat exchanger calculated by a one-dimensional thermodynamic computation analysis program as T nBoundary conditions at time, computational fluid dynamics software CFX completion T nAfter the time is calculated, a one-dimensional thermal hydraulic calculation analysis program reads T calculated by computational fluid dynamics (CFX) software nThe temperature, pressure and steam content in the containment vessel at the time of day and T n+1Calculating the time;
And 4, step 4: repeating the step 3 until the required calculation time span is reached; and finally, obtaining the values of the temperature, the pressure and the steam share in the containment after the passive containment waste heat discharge system is put into operation.
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| CN110362918B (en) * | 2019-07-12 | 2020-12-22 | 西安交通大学 | Calculation method for condensation and evaporation coupling on two sides of containment vessel of pressurized water reactor |
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| CN112307626B (en) * | 2020-11-02 | 2021-09-03 | 西安交通大学 | Operation and influence analysis method for multiple groups of passive heat export systems in containment |
| CN113283189B (en) * | 2021-04-30 | 2022-07-26 | 西安交通大学 | Cross-dimension coupling analysis method for containment and passive containment air cooling system |
| CN113704959B (en) * | 2021-07-12 | 2024-04-09 | 中国核电工程有限公司 | Simulation method and system for heat exchanger type passive containment cooling system |
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| CN114201870B (en) * | 2021-12-08 | 2024-06-25 | 东北电力大学 | Adaptive multi-scale coupling method for analyzing passive characteristics of nuclear power plant |
| CN115497653B (en) * | 2022-09-19 | 2023-05-02 | 西安交通大学 | Method for analyzing operation characteristics of passive containment air cooling system |
Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| KR101651466B1 (en) * | 2015-04-02 | 2016-08-29 | 한국원자력연구원 | Verification test device for passive residual heat removal system of a research reactor |
| CN107704674A (en) * | 2017-09-26 | 2018-02-16 | 吉林省电力科学研究院有限公司 | The method for numerical simulation of air cooling tubes condenser water vapor condensation process |
| CN109299536A (en) * | 2018-09-20 | 2019-02-01 | 西安交通大学 | A kind of large pressurized water reactor nuclear power plant voltage-stablizer water seal forming process calculation method |
Family Cites Families (1)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN108846163B (en) * | 2018-05-10 | 2022-05-31 | 岭东核电有限公司 | Method for determining gas phase initial state before containment test |
-
2019
- 2019-03-15 CN CN201910195647.7A patent/CN109902433B/en active Active
Patent Citations (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| KR101651466B1 (en) * | 2015-04-02 | 2016-08-29 | 한국원자력연구원 | Verification test device for passive residual heat removal system of a research reactor |
| CN107704674A (en) * | 2017-09-26 | 2018-02-16 | 吉林省电力科学研究院有限公司 | The method for numerical simulation of air cooling tubes condenser water vapor condensation process |
| CN109299536A (en) * | 2018-09-20 | 2019-02-01 | 西安交通大学 | A kind of large pressurized water reactor nuclear power plant voltage-stablizer water seal forming process calculation method |
Non-Patent Citations (3)
| Title |
|---|
| AP1000非能动余热排出***建模与瞬态数值分析;王伟伟等;《原子能科学技术》;20111231;第45卷(第12期);1456-1461 * |
| 子通道程序与CFD程序的耦合方法研究;桂民洋等;《原子能科学技术》;20181130;第52卷(第11期);1962-1967 * |
| 非能动余热排出换热器换热能力数值分析;张文文等;《原子能科学技术》;20150630;第49卷(第6期);1032-1038 * |
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