CN109902433A - Across the dimension coupling process of presurized water reactor passive containment residual heat removal system - Google Patents
Across the dimension coupling process of presurized water reactor passive containment residual heat removal system Download PDFInfo
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Abstract
The invention discloses a kind of across dimension coupling process of presurized water reactor passive containment residual heat removal system, and steps are as follows: 1, establishing passive containment residual heat removal system model using one-dimensional Thermal hydraulic calculation analysis program;2, containment three-dimensional computations flow dynamics analysis model is established, and is calculated using cfdrc CFX;3, exchanging for one-dimensional Thermal hydraulic calculation analysis program and cfdrc CFX data is completed;4, step (3) are repeated, the requirement of time is calculated until reaching.This method can be calculated accurately under the action of passive containment residual heat removal system, and the value of temperature, pressure and steam share in containment is of great significance to the safety analysis after accident.
Description
Technical field
The invention belongs to nuclear reactor safety analysis technical fields, and in particular to after accident, passive containment waste heat
Across the dimension coupling analytical method that discharge system influences the distribution of containment flow field after putting into operation.
Background technique
Containment is that last one barrier of the radioactive substance in reactor to outward leakage is prevented under accident conditions, because
The integrality of this containment is most important for nuclear reactor safety.Traditional PWR nuclear power plant usually utilizes containment to spray
Heat derives inside containment after generation cut accident are prevented containment because of over-temp and over-pressure lost integrity by leaching system.So
And when the beyond design basis accident of the forfeiture external power such as whole audience power-off occurs, containment spray system can be due to losing external power
Failure, so that the integrality of containment be made to face huge threat.
Currently, there are three types of the method analyzed nuclear reactor safety of educational circles is general: 1. network analyses, such as RELAP5 program,
The unidimensional systems such as TRACE program analyze program;2. computational fluid dynamics (CFD) is simulated, such as ANSYS CFX software;3. son
Multichannel analysis program, such as COBRA program.Wherein, three-dimensional thermal technology's hydraulic phenomenon that unidimensional system analysis program can not be complicated into
Row analytical calculation;CFD approach modeling is complicated, and time-consuming for transient state calculating, and model is perfect not to the utmost, has for nuclear reactor safety analysis
Compared with big limitation;Subchannel analysis Method Modeling is simpler, requires calculating low but same to three-dimensional phenomenon in analysis containment
With significant limitation.
Design extend operating condition, especially major accident in the case of, the gas in containment include air, vapor and
Hydrogen etc., in nature, the flowing and heat transfer of these gases are three-dimensional phenomenon.Containment under containment spray system effect
Interior thermal environment is relatively uniform, can be solved well using traditional lumped parameter program;However, for passive system
The non-uniform stratification of hot gas of local thermal technology's parameter distribution or heat point may be then presented in containment thermal-hydraulic phenomenon under system effect
The phenomenon that layer, lumped parameter program traditional at this time can not carry out accurate simulation, and three-dimensional computations hydrodynamics program then can be with
It is simulated well.But current three-dimensional computations hydrodynamics program (such as general-purpose computations hydrodynamics program CFX, FLUENT;
Dedicated containment thermal-hydraulic computation fluid dynamics codes GASFLOW etc.) not comprising the meter of passive residual heat removal system
Module is calculated, application of this class method in terms of passive containment thermal-hydraulic phenomenal research is limited.Therefore in order to further
Study three-dimensional thermal technology's hydraulic phenomenon in the lower containment of remaining heat-extraction system effect, need to be directed to computation fluid dynamics codes (CFX) into
Row secondary development makes CFX program have the ability for simulating remaining heat-extraction system.
More than Liu of Tsinghua University et al. based on RELAP5 and CFX program, parallel virtual machine technology and CFX user are utilized
Function is programmed, and develops RELAP5/CFX coupling procedure.In single-phase range, tested first with the horizontal pipe problem of spurting
The correctness coupled between program is demonstrate,proved.Then, it is simulated for double-T shaped adapter tube combined experiments.Relative to individual
RELAP5 program, coupling procedure can preferably disclose true physical phenomenon.Perfect by subsequent exploitation, coupling procedure is available
The problem of there is significant three-dimensional hybrid phenomenons in reactor safety analysis.Liu Yu also passes through research channel program
(COBRA-IV) and computation fluid dynamics codes (CFX) internal structure the interface to intercouple, is developed, is changed using the display time
For the thought of mode and Region Decomposition, data are exchanged by peripheral control program, establish COBRA-IV/CFX coupling procedure, it is real
The component showed in multi-scale coupling simulation is coupled with local scale.For 5X5 cluster component, stable state and transient state have been carried out respectively
The coupling of problem calculates, the accuracy that result verification coupling procedure calculates.
The Anderson N in the U.S. et al. is for superhigh temperature air cooling under better forecast analysis nominal situation and accident conditions
Complicated thermal-hydraulic phenomenon in heap, RELAP5-3D and CFD software FLUENT are coupled by they.They choose air cooled reactor
Interior coolant from reactor core enter upper chamber after hot mixing phenomenon, very high temperature gas cooled reactor is modeled using RELAP5-3D, use
FLUENT models the upper chamber of part, and the exit condition of RELAP5 provides inlet boundary condition for FLUENT.Pass through coupling
Close, complicated Three Dimensional Thermal mixing phenomena can be simulated accurately very much in upper chamber comes, and do not have to entire reactor into
Row CFD modeling, has saved a large amount of calculating costs.Verified, the calculated result of coupling is accurate believable.
Davide Bertolotto of Switzerland et al. most preferably estimates three-dimensional computations hydrodynamics software CFX with thermal-hydraulic
Program TRACE is calculated to be coupled together and carried out corresponding verifying.The operating condition of coupling procedure first verified that is filled with the water of fluid
Flat round pipe spurts problem;The second step of verifying is calculated for double-T shaped adapter tube mixed problem.Calculated result shows three-dimensional simulation
As a result there is big advantage compared with one-dimensional.
Summary of the invention
To solve the above-mentioned problems, the present invention provides a kind of presurized water reactor passive containment residual heat removal systems across dimension
Coupling process.This method can not only calculate the various thermal-hydraulic phenomenons in passive containment residual heat removal system, can be with
It accurately calculates under the effect of passive containment residual heat removal system, the value of temperature, pressure and steam share in containment.
In order to achieve the above objectives, present invention employs following technical solutions:
A kind of across dimension coupling process of presurized water reactor passive containment residual heat removal system, for non-passive safety after accident
Shell residual heat removal system put into operation after containment environment, by one-dimensional Thermal hydraulic calculation analysis program to non-passive safety
Shell residual heat removal system model and using three-dimensional computations hydrodynamics software CFX to containment inside and non-passive safety
The heat exchanger section of shell residual heat removal system carries out modeling analysis, obtains the effect in passive containment residual heat removal system
Under, the value of temperature, pressure, steam share in containment realizes one-dimensional to the three-dimensional coupling analysis across dimension;This method is specific
Include the following steps:
Step 1: according to the structure of passive containment residual heat removal system, passing through the one-dimensional thermal-hydraulic meter of Nuclear Power System
Point counting analysis program establishes passive containment residual heat removal system model;Passive containment residual heat removal system model includes changing
Hot device computation model, ascent stage pipeline model, descending branch pipeline model, heat-exchanging water tank model and heat-exchanging water tank moisturizing model, from
And the thermal-hydraulic response process for calculating passive containment residual heat removal system after putting into operation is simulated, it obtains heat exchanger and changes
The key parameter of heat pipe wall temperature, natural circulation flow passes through stream between these passive containment residual heat removal system models
Road connection, realizes the exchange of quality, momentum and energy between each system model;
Step 2: the heat exchanger in containment and containment being built using commercial Grid Generation Software ICEM CFD
Mould imports containment and heat exchanger geometrical model in cfdrc CFX, by cfdrc
Quality source item and momentum source term are added in the governing equation of CFX, to consider in computational domain since the steam containing incoagulable gas is cold
Mass loss caused by solidifying and energy loss realize cfdrc CFX to the steam containing incoagulable gas in safety
The calculating of condensation number in shell;
Step 3: one-dimensional Thermal hydraulic calculation analysis program passes through temperature, pressure and the steam in Tn-1 moment containment
Share completes the calculating at Tn moment as boundary condition, obtains Tn moment heat exchanger heat-exchanging tube wall temperature, Fluid Mechanics Computation is soft
Part CFX reads the boundary of heat exchanger heat-exchanging tube wall temperature that one-dimensional Thermal hydraulic calculation analysis program is calculated as the Tn moment
Condition, after cfdrc CFX completes the calculating at Tn moment, one-dimensional Thermal hydraulic calculation analysis program, which is read, calculates stream
Temperature, pressure and steam share in the containment at the Tn moment that mechanics software CFX is calculated, and carry out the Tn+1 moment
Calculating;
Step 4: repeating step (3), until reaching the calculating time span of requirement;It is final to obtain more than the passive containment
After hot discharge system puts into operation, the value of temperature, pressure and steam share in containment.
The present invention has the following advantages and beneficial effects:
It can be carried out the deficiency of One Dimension Analysis calculating 1. overcoming system analysis program only, realize containment flow field thermal field
Three-dimensional computations;
2. this method, which has simulation passive containment residual heat removal system, acts on stratification of hot gas phenomenon in lower containment
Ability, avoid complicated three-dimensional modeling;
3. passive containment residual heat removal system program and cfdrc CFX are relatively independent, can be independent
Carry out operation;
4. capableing of the condensation process of vapor of the accurate simulation containing incoagulable gas heat exchanger near wall in containment;
5. it can calculate under a variety of accident conditions, it is corresponding in containment after passive containment residual heat removal system puts into operation
Fluid flowing heat transfer phenomenon;
6. computing resource consumes less, calculating speed is fast and computational solution precision is high.
The present invention has passed through it was verified that this method being capable of accurate simulation passive containment residual heat removal system investment
Three-dimensional thermal technology's hydraulic phenomenon after operation in containment, the presurized water reactor passive containment residual heat removal system that proposes in the present invention
Across dimension coupling process not only makes cfdrc CFX have the transient state mistake of the passive remaining heat-extraction system operation of calculating
The ability of journey, while solving network analysis software again only and can be carried out the limitation of one-dimensional calculating analysis.
Detailed description of the invention
Fig. 1 is passive containment residual heat removal system schematic diagram.
Fig. 2 is that passive containment residual heat removal system model node divides schematic diagram.
Fig. 3 is containment and heat-exchanger model.
Fig. 4 is coupled modes.
Specific embodiment:
The invention will be described in further detail with reference to the accompanying drawings and detailed description:
The present invention provides a kind of across dimension coupling process of presurized water reactor passive containment residual heat removal system, specific methods
It is as follows:
Step 1: any known nuclear power is used according to Fig. 1 presurized water reactor passive containment residual heat removal system schematic diagram
The one-dimensional Thermal hydraulic calculation analysis program of system establishes non-passive safety such as RELAP5 program, TRAC program, RETRAN program
Shell residual heat removal system model.Passive containment residual heat removal system model includes heat exchanger design model, rises segment pipe
Model, descending branch pipeline model, heat-exchanging water tank model and heat-exchanging water tank moisturizing model calculate more than passive containment to simulate
Thermal-hydraulic response process of the hot discharge system after putting into operation, obtains heat exchanger heat-exchanging tube wall temperature, natural circulation flow
Key parameter.
The node division schematic diagram of passive containment residual heat removal system model as shown in Fig. 2, include heat-exchanging water tank,
Heat exchanger, ascent stage and descending branch pipeline.The model includes 40 control volumes, and wherein heat-exchanging water tank has divided 5 control volumes,
Descending branch 1 divides 5 control volumes, lower that section 2 is divided 5 control volumes, and heat exchanger divides 10 control volumes, and the ascent stage 1 divides 10
A control volume, ascent stage 2 divide 5 control volumes.Then two adjacent control volumes are connected using runner, simulated between control volume
Mass transfer, energy transmission and the momentum transfer process of (between system equipment).
Step 2: the heat exchanger in containment and containment being built using commercial Grid Generation Software ICEM CFD
Mould, as shown in figure 3, containment and heat exchanger geometrical model are imported in cfdrc CFX, by calculating fluid
Quality source item and momentum source term are added in the governing equation of machine software CFX, to consider in computational domain due to containing incoagulable gas
Steam condense caused by mass loss and energy loss, realize cfdrc CFX to the steaming containing incoagulable gas
The calculating of vapour condensation number in containment;
Condensation number of the steam containing incoagulable gas in containment is being calculated using cfdrc CFX
When, do not consider two-phase fluid, does not consider the flowing of condensate film.Mass loss calculating formula wherein when water recovery is as follows:
In formula:
Cu--- regulation coefficient;
Area/m of A --- condensing wall2;
T --- steam temperature/DEG C;
Twall--- wall surface temperature/DEG C;
hlg--- the saturated vapor latent heat of vaporization/Jkg-1;
ρg--- water vapor density/kgm-3;
ρn--- on-condensible gas density/kgm-3。
The energy loss of water recovery can be calculated by the following formula:
H0=m0(Tcp,m-Twallcp,g)
In formula: m0--- steam condensation rate/kgs-1;
cp,m--- level pressure thermal capacitance/Jkg of mixed gas-1·K-1;
cp,g--- level pressure thermal capacitance/Jkg of on-condensible gas-1×K-1;
T --- steam temperature/DEG C;
Tref--- reference temperature when enthalpy is 0,273.15K.
Step 3: as shown in figure 4, one-dimensional Thermal hydraulic calculation analysis program passes through temperature, the pressure in Tn-1 moment containment
Power and steam share complete the calculating at Tn moment as boundary condition, obtain Tn moment heat exchanger heat-exchanging tube wall temperature, calculate
Hydrodynamics software CFX reads heat exchanger heat-exchanging tube wall temperature that one-dimensional Thermal hydraulic calculation analysis program is calculated as Tn
The boundary condition at moment, after cfdrc CFX completes the calculating at Tn moment, one-dimensional Thermal hydraulic calculation analysis program
Temperature, pressure and the steam share in the containment at the Tn moment that cfdrc CFX is calculated are read, is gone forward side by side
The calculating at row Tn+1 moment;
Step 4: carrying out future time step size computation, repeat step (3);Until reaching the calculating time span of requirement.
It is final to obtain after passive containment residual heat removal system puts into operation, temperature in containment, pressure and steam share
Value.
Claims (1)
1. a kind of across dimension coupling process of presurized water reactor passive containment residual heat removal system, it is characterised in that: for after accident
Passive containment residual heat removal system put into operation after containment environment, pass through one-dimensional Thermal hydraulic calculation analysis program pair
Passive containment residual heat removal system model and using three-dimensional computations hydrodynamics software CFX to containment inside and
The heat exchanger section of passive containment residual heat removal system carries out modeling analysis, obtains in passive containment Residual heat removal system
Under the action of system, the value of temperature, pressure, steam share in containment is realized one-dimensional to the three-dimensional coupling analysis across dimension;
Across dimension coupling process is somebody's turn to do to specifically comprise the following steps:
Step 1: according to the structure of passive containment residual heat removal system, being calculated and divided by the one-dimensional thermal-hydraulic of Nuclear Power System
Analysis program establishes passive containment residual heat removal system model;Passive containment residual heat removal system model includes heat exchanger
Computation model, ascent stage pipeline model, descending branch pipeline model, heat-exchanging water tank model and heat-exchanging water tank moisturizing model, thus mould
The quasi- thermal-hydraulic response process for calculating passive containment residual heat removal system after putting into operation, obtains heat exchanger heat-exchanging tube
The key parameter of wall temperature, natural circulation flow passes through runner between these passive containment residual heat removal system models and connects
It connects, realizes the exchange of quality, momentum and energy between each system model;
Step 2: the heat exchanger in containment and containment is modeled using Grid Generation Software ICEM CFD, it will be safe
Shell and heat exchanger geometrical model import in cfdrc CFX, pass through the controlling party in cfdrc CFX
Quality source item and momentum source term are added in journey, to consider quality caused by condensing in computational domain due to the steam containing incoagulable gas
Loss and energy loss, realization cfdrc CFX condensation number in containment to the steam containing incoagulable gas
It calculates;
Step 3: one-dimensional Thermal hydraulic calculation analysis program passes through temperature, pressure and the steam share in Tn-1 moment containment
The calculating that the Tn moment is completed as boundary condition, obtains Tn moment heat exchanger heat-exchanging tube wall temperature, cfdrc CFX
The boundary condition of heat exchanger heat-exchanging tube wall temperature that one-dimensional Thermal hydraulic calculation analysis program is calculated as the Tn moment is read,
After cfdrc CFX completes the calculating at Tn moment, one-dimensional Thermal hydraulic calculation analysis program, which is read, calculates fluid force
Temperature, pressure and the steam share in the containment at the Tn moment that software CFX is calculated are learned, and carries out the meter at Tn+1 moment
It calculates;
Step 4: repeating step (3), until reaching the calculating time span of requirement;Final obtain is arranged in passive containment waste heat
After system puts into operation out, the value of temperature, pressure and steam share in containment.
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Cited By (10)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
CN110362918A (en) * | 2019-07-12 | 2019-10-22 | 西安交通大学 | A kind of condensation of pressurized water reactor containment two sides and evaporation coupling calculation |
CN110489796A (en) * | 2019-07-17 | 2019-11-22 | 哈尔滨工程大学 | A kind of Effective judgement method of the nuclear reactor heat derives system based on heat pipe |
CN111274748A (en) * | 2020-03-18 | 2020-06-12 | 西安交通大学 | Cross-dimension coupling calculation method for pool type sodium-cooled fast reactor passive waste heat removal system |
CN111651944A (en) * | 2020-06-05 | 2020-09-11 | 中国原子能科学研究院 | Nuclear reactor computing system |
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Citations (4)
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 |
CN108846163A (en) * | 2018-05-10 | 2018-11-20 | 岭东核电有限公司 | A method of for determining that containment tests preceding gas phase original state |
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 |
-
2019
- 2019-03-15 CN CN201910195647.7A patent/CN109902433B/en active Active
Patent Citations (4)
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 |
CN108846163A (en) * | 2018-05-10 | 2018-11-20 | 岭东核电有限公司 | A method of for determining that containment tests preceding gas phase original state |
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 |
---|
张文文等: "非能动余热排出换热器换热能力数值分析", 《原子能科学技术》 * |
桂民洋等: "子通道程序与CFD程序的耦合方法研究", 《原子能科学技术》 * |
王伟伟等: "AP1000非能动余热排出系统建模与瞬态数值分析", 《原子能科学技术》 * |
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