CN105653869B - A kind of supercritical water reactor reactor core Three dimensional transient method for analyzing performance - Google Patents
A kind of supercritical water reactor reactor core Three dimensional transient method for analyzing performance Download PDFInfo
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Abstract
The invention discloses a kind of supercritical water reactor reactor core Three dimensional transient method for analyzing performance to include：Step 1：It executes reactor core stable state to calculate, power parameter, thermal parameter is provided, execute iteration coupling and calculate until reactor core steady state power parameter and thermal parameter are restrained；Step 2：Reactor core original state and component cross-section library are provided；Step 3：It executes transient state to calculate, power parameter, thermal parameter is provided, execute iteration coupling and calculate until reactor core transient power parameter and thermal parameter are restrained；Step 4：The fine power distribution of hot component lattice cell scale is obtained, hot component subchannel analysis is carried out, finally provides safety evaluation key parameter；Step 5：Judge whether the safety evaluation key parameter is more than corresponding transient state or fail- safe limit value, realize feedback that can be between accurate description physics and thermal-hydraulic, more accurate reactor core three-dimensional power distribution, the technique effect of the transient process and accident process of true simulation supercritical water reactor are provided.
Description
Technical field
The present invention relates to nuclear reactor designs research field more particularly to a kind of supercritical water reactor reactor core Three dimensional transient performances
Analysis method.
Background technology
The operating condition of supercritical water reactor (SCWR) is more than the thermodynamic critical point (374 DEG C, 22.1MPa) of water, system
The thermal efficiency is high, good economy performance, but simultaneously, compared with conventional water cooled reator, supercritical water reactor operating parameter greatly improves, and reactor core
Structure and coolant flow are relative complex, bring the technical barriers such as a large amount of core physics, thermal technology-waterpower and safety analysis,
Wherein, strong nuclear heat coupled characteristic is one of the key technology difficulty of supercritical water reactor Core Design and performance evaluation.
In the heteropathy event of supercritical water reactor, most of, control rod remarkable action things related to control rod action
Part will cause the distribution distortion of supercritical water reactor core power, along with strong physics and thermal technology-Seepage-stress coupling effect, power point
Cloth variation will directly affect supercritical water reactor fuel maximum clad temperature, and it is that supercritical water reactor is very heavy that clad temperature, which does not transfinite,
The Transient safety analysis rule wanted puts heap or one-dimensional neutron dynamics model can not be correct for power abnormal distribution event
The spatial distribution for describing power, can not accurately calculate power and change with time, and to ensure the envelope calculated, just must be introduced into
A large amount of conservative is it is assumed that in addition, supercritical water reactor is due to inherently having strong nuclear heat coupled characteristic, reactivity and power point
The transient process of cloth anomalous event is more complicated, and conservative approach cannot provide its true response process, this makes designer
Member is difficult to carry out in-depth study and analysis to heteropathy event, only couples three-dimensional Neutron Time-Space Kinetics and thermal technology-
Hydraulics carries out Analysis of Transient, and the feedback between ability accurate description physics and thermal technology-waterpower provides more accurate three-dimensional
Power is distributed, the transient process and accident process of true simulation supercritical water reactor.
In the prior art, for supercritical water reactor power abnormal distribution event, the transient state analyzing method used in the world,
Neutron dynamics part does not have the three-dimensional power calculation ability of reactor core nuclear heat coupling, it is difficult to true using point heap or one-dimensional model
The real or accurate simulation such as transient process of reactivity and power abnormal distribution event.
In conclusion present inventor is during inventive technique scheme in realizing the embodiment of the present application, in discovery
Technology is stated at least to have the following technical problems：
In the prior art, existing supercritical water reactor power distribution transient state analyzing method, which exists, does not have reactor core nuclear heat coupling
Close three-dimensional power calculation ability, it is difficult to the true or accurate simulation such as transient process of reactivity and power abnormal distribution event
The technical issues of.
Invention content
The present invention provides a kind of supercritical water reactor reactor core Three dimensional transient method for analyzing performance, solve existing overcritical
Water-water reactor power distribution transient state analyzing method, which exists, does not have the three-dimensional power calculation ability of reactor core nuclear heat coupling, it is difficult to true or accurate
The technical issues of simulation such as transient process of reactivity and power abnormal distribution event, realizing being capable of accurate description physics
With the feedback between thermal technology-waterpower, more accurate reactor core three-dimensional power distribution, the transient state of true simulation supercritical water reactor are provided
The technique effect of process and accident process.
In order to solve the above technical problems, the embodiment of the present application provides a kind of supercritical water reactor reactor core Three dimensional transient performance point
Analysis method, the method includes：
Step 1：Supercritical water reactor reactor core three-dimensional steady state physics-thermal-hydraulic coupling module executes reactor core stable state and calculates, heap
Core fuel management module provides power parameter to subchannel thermal technology-hydraulic module, and subchannel thermal technology-hydraulic module is to reactor fuel
Management module provides thermal parameter, executes iteration coupling and calculates until reactor core steady state power parameter and thermal parameter are restrained；
Step 2：Reactor core three-dimensional steady state physics-thermal-hydraulic coupling module is to supercritical water reactor reactor core Three dimensional transient physics-
Thermal-hydraulic coupling module provides reactor core original state and component cross-section library；
Step 3：Supercritical water reactor reactor core Three dimensional transient physics-thermal-hydraulic coupling module executes transient state and calculates, in three-dimensional
Period of the day from 11 p.m. to 1 a.m lost motion mechanics module provides power parameter to subchannel thermal technology-hydraulic module, and subchannel thermal technology-hydraulic module is into three-dimensional
Period of the day from 11 p.m. to 1 a.m lost motion mechanics module provides thermal parameter, executes iteration coupling and calculates until reactor core transient power parameter and thermal parameter are received
It holds back；
Step 4：Power is carried out in reactor core calculating to hot component to reconstruct to obtain the fine power point of hot component lattice cell scale
Cloth carries out hot component subchannel analysis using subchannel thermal technology-hydraulic module again, finally provides safety evaluation key parameter；
Step 5：Judge whether the safety evaluation key parameter is more than corresponding transient state or fail- safe limit value, and evaluation is super
Security performance of the critical water-water reactor reactor core under transient process.
Further, the safety evaluation key parameter includes：Maximum involucrum wall surface temperature, pellet heat content.
Further, using few group cross-section in reactor core three-dimensional Neutronics calculation, few group cross-section is about thermal parameter and in advance
Cross-section library is pre-machined by the way of piecewise interpolation and is used for reactor core three-dimensional neutronics module for the variation of setting parameter, described pre-
Setting parameter includes：Fuel-assembly burn-up, whether there is or not control rods.
Further, the execution iteration coupling calculates until reactor core steady state power parameter and the specific packet of thermal parameter convergence
It includes：
Start；
Input file is read, initialization component lacks group cross-section, reactor core neutron flux；
Subchannel thermal technology's module stable state is carried out to calculate；
It is updated section；
Three-dimensional neutronics module stable state is carried out to calculate；
Subchannel thermal technology's module stable state is carried out to calculate；
Judge whether core power distribution restrains, if otherwise return to step re-starts update section；If then stable state meter
Terminate, is calculated into transient state.
Further, the supercritical water reactor reactor core Three dimensional transient physics-thermal-hydraulic coupling module executes transient state and calculates
It specifically includes：
Start transient state to calculate；
Time step update is carried out, the initial value at n moment is prepared；
It carries out subchannel thermal technology's module transient state and calculates a time step；
It is updated section；
It carries out three-dimensional Neutron Time-Space Kinetics module transient state and calculates first time step；
Judge whether core power distribution restrains, executes time step update if otherwise returning, prepare the initial value at n moment；If
It is then n=n+1；Judge whether tn is less than T, wherein tn is that the n-th time step corresponds to the time, and T is that preassigned transient state is calculated to T
Moment executes time step update if then returning, prepares the initial value at n moment；Terminate if otherwise calculating.
Further, the supercritical water reactor reactor core three-dimensional steady state physics-thermal-hydraulic coupling module executes reactor core stable state
It calculates and the supercritical water reactor reactor core Three dimensional transient physics-thermal-hydraulic coupling module executes transient state and calculates, be all made of identical
Space method for solving：Second kind boundary condition locking nub green function method.In this way to ensure that three-dimensional steady state-transient state calculates analysis
The self-consistency of Neutronics calculation in the process.
Further, it is described execute reactor core Three dimensional transient physical computing three-dimensional Neutron Time-Space Kinetics module use when
Between discrete method be Euler's method backward.Wherein, Euler's method has absolutely-stability backward, and convenient for the serial of program
Coupling exploitation.
One or more technical solutions provided in the embodiments of the present application have at least the following technical effects or advantages：
As a result of supercritical water reactor reactor core Three dimensional transient method for analyzing performance is designed as to include：Step 1：It is overcritical
Water-water reactor reactor core three-dimensional steady state physics-thermal-hydraulic coupling module executes reactor core stable state and calculates, and in-core fuel management module is logical to son
Road thermal technology-hydraulic module provides power parameter, and subchannel thermal technology-hydraulic module provides thermal technology's ginseng to in-core fuel management module
Number executes iteration coupling and calculates until reactor core steady state power parameter and thermal parameter are restrained；Step 2：Reactor core three-dimensional steady state physics-
Thermal-hydraulic coupling module provides reactor core original state to supercritical water reactor reactor core Three dimensional transient physics-thermal-hydraulic coupling module
With component cross-section library；Step 3：Supercritical water reactor reactor core Three dimensional transient physics-thermal-hydraulic coupling module executes transient state and calculates, and three
It ties up Neutron Time-Space Kinetics module and provides power parameter to subchannel thermal technology-hydraulic module, subchannel thermal technology-hydraulic module is to three
It ties up Neutron Time-Space Kinetics module and thermal parameter is provided, execute iteration coupling and calculate until reactor core transient power parameter and thermal technology join
Number convergence；Step 4：Power is carried out in reactor core calculating to hot component to reconstruct to obtain the fine power point of hot component lattice cell scale
Cloth carries out hot component subchannel analysis using thermal technology's module again, finally provides safety evaluation key parameter；Step 5：Judge institute
State whether safety evaluation key parameter is more than corresponding transient state or fail- safe limit value, evaluation supercritical water reactor reactor core is in transient state mistake
The technical solution of security performance under journey carries out transient state mistake by coupling three-dimensional Neutron Time-Space Kinetics with thermal technology-hydraulics
Journey is analyzed, and neutron dynamics part uses threedimensional model, so that it is had the three-dimensional power calculation ability of reactor core nuclear heat coupling, is realized super
The technique effect of critical water-water reactor reactor core Three dimensional transient analysis；So efficiently solving existing supercritical water reactor power distribution wink
State analysis method, which exists, does not have the three-dimensional power calculation ability of reactor core nuclear heat coupling, it is difficult to which true or accurate simulation is for example reacted
It the technical issues of transient process of property and power abnormal distribution event, realizes by establishing reactor core three-dimensional steady state-transient state physics-
Thermal-hydraulic couples calculation process, and feedback that can be between accurate description physics and thermal technology-waterpower provides more accurate reactor core three
Tie up power distribution, the technique effect of the transient process and accident process of true simulation supercritical water reactor.
Further, this method can true simulation supercritical water reactor reactor core transient process, improve to supercritical water reactor
The understanding of reactor core transient condition, more accurately estimation safety allowance, improvement Core Design simultaneously improve heap core performance.
Description of the drawings
To make the objectives, technical solutions, and advantages of the present invention clearer, with reference to embodiment and attached drawing, to this
Invention is described in further detail, and exemplary embodiment of the invention and its explanation are only used for explaining the present invention, do not make
For limitation of the invention.
Fig. 1 is that supercritical water reactor reactor core three-dimensional steady state-transient state physics-thermal-hydraulic couples calculation process schematic diagram；
Fig. 2 is supercritical water reactor reactor core Three dimensional transient method for analyzing performance stable state calculation process schematic diagram；
Fig. 3 illustrates for supercritical water reactor reactor core Three dimensional transient method for analyzing performance transient state calculation process；
Fig. 4 is Euler's method instantaneous neutron calculation process schematic diagram backward.
Specific implementation mode
The present invention provides a kind of supercritical water reactor reactor core Three dimensional transient method for analyzing performance, solve existing overcritical
Water-water reactor power distribution transient state analyzing method, which exists, does not have the three-dimensional power calculation ability of reactor core nuclear heat coupling, it is difficult to true or accurate
The technical issues of simulation such as transient process of reactivity and power abnormal distribution event, realizing being capable of accurate description physics
With the feedback between thermal technology-waterpower, more accurate reactor core three-dimensional power distribution, the transient state of true simulation supercritical water reactor are provided
The technique effect of process and accident process.
Technical solution in the application implementation is to solve above-mentioned technical problem.General thought is as follows：
Use supercritical water reactor reactor core Three dimensional transient method for analyzing performance is designed as include：Step 1：Supercritical water reactor
Reactor core three-dimensional steady state physics-thermal-hydraulic coupling module executes reactor core stable state and calculates, and in-core fuel management module is hot to subchannel
Work-hydraulic module provides power parameter, and subchannel thermal technology-hydraulic module provides thermal parameter to in-core fuel management module, holds
Row iteration coupling calculates until reactor core steady state power parameter and thermal parameter are restrained；Step 2：Reactor core three-dimensional steady state physics-thermal technology
Seepage-stress coupling module provides reactor core original state and group to supercritical water reactor reactor core Three dimensional transient physics-thermal-hydraulic coupling module
Part cross-section library；Step 3：Supercritical water reactor reactor core Three dimensional transient physics-thermal-hydraulic coupling module executes transient state and calculates, in three-dimensional
Period of the day from 11 p.m. to 1 a.m lost motion mechanics module provides power parameter to subchannel thermal technology-hydraulic module, and subchannel thermal technology-hydraulic module is into three-dimensional
Period of the day from 11 p.m. to 1 a.m lost motion mechanics module provides thermal parameter, executes iteration coupling and calculates until reactor core transient power parameter and thermal parameter are received
It holds back；Step 4：Power is carried out in reactor core calculating to hot component to reconstruct to obtain the fine power distribution of hot component lattice cell scale, then
It is secondary to carry out hot component subchannel analysis using thermal technology's module, finally provide safety evaluation key parameter；Step 5：Judge the peace
Whether full evaluation key parameter is more than corresponding transient state or fail- safe limit value, and evaluation supercritical water reactor reactor core is under transient process
Security performance technical solution, that is, pass through and couple three-dimensional Neutron Time-Space Kinetics and carry out transient process point with thermal technology-hydraulics
Analysis, neutron dynamics part use threedimensional model, so that it is had the three-dimensional power calculation ability of reactor core nuclear heat coupling, realize overcritical
The technique effect of water-water reactor reactor core Three dimensional transient analysis；So efficiently solving existing supercritical water reactor power distribution transient state point
Analysis method, which exists, does not have the three-dimensional power calculation ability of reactor core nuclear heat coupling, it is difficult to true or accurate simulation such as reactivity and
The technical issues of transient process of power abnormal distribution event, realizes by establishing reactor core three-dimensional steady state-transient state physics-thermal technology
Seepage-stress coupling calculation process, feedback that can be between accurate description physics and thermal technology-waterpower provide more accurate reactor core three-dimensional work(
Rate is distributed, the technique effect of the transient process and accident process of true simulation supercritical water reactor.
In order to better understand the above technical scheme, in conjunction with appended figures and specific embodiments to upper
Technical solution is stated to be described in detail.
Embodiment one：
In embodiment one, a kind of supercritical water reactor reactor core Three dimensional transient method for analyzing performance is provided, please refer to Fig.1-
Fig. 4, the method includes：
Step 1：Supercritical water reactor reactor core three-dimensional steady state physics-thermal-hydraulic coupling module executes reactor core stable state and calculates, heap
Core fuel management module provides power parameter to subchannel thermal technology-hydraulic module, and subchannel thermal technology-hydraulic module is to reactor fuel
Management module provides thermal parameter, executes iteration coupling and calculates until reactor core steady state power parameter and thermal parameter are restrained；
Step 2：Reactor core three-dimensional steady state physics-thermal-hydraulic coupling module is to supercritical water reactor reactor core Three dimensional transient physics-
Thermal-hydraulic coupling module provides reactor core original state and component cross-section library；
Step 3：Supercritical water reactor reactor core Three dimensional transient physics-thermal-hydraulic coupling module executes transient state and calculates, in three-dimensional
Period of the day from 11 p.m. to 1 a.m lost motion mechanics module provides power parameter to subchannel thermal technology-hydraulic module, and subchannel thermal technology-hydraulic module is into three-dimensional
Period of the day from 11 p.m. to 1 a.m lost motion mechanics module provides thermal parameter, executes iteration coupling and calculates until reactor core transient power parameter and thermal parameter are received
It holds back；
Step 4：Power is carried out in reactor core calculating to hot component to reconstruct to obtain the fine power point of hot component lattice cell scale
Cloth carries out hot component subchannel analysis using thermal technology's module again, finally provides safety evaluation key parameter；
Step 5：Judge whether the safety evaluation key parameter is more than corresponding transient state or fail- safe limit value, and evaluation is super
Security performance of the critical water-water reactor reactor core under transient process.
Wherein, in the embodiment of the present application, the safety evaluation key parameter includes but not limited to：Maximum involucrum wall surface temperature
Degree, pellet heat content.
Wherein, in practical applications, the corresponding safety limit of above-mentioned safety evaluation key parameter is respectively：Maximum involucrum wall
Safety limit is 850 DEG C under the temperature transient operating mode of face, and safety limit is 1260 DEG C under accident conditions；Under pellet heat content transient condition
Safety limit is 170cal/g, and safety limit is 230cal/g under accident conditions.(under accident conditions, safety criterion can not require
Now excessive reactor core damage；Under transient condition, safety criterion requires do not occur systemic fuel rod damage, fuel pellet damage.)
Wherein, in the embodiment of the present application, in reactor core calculating using few group cross-section, few group cross-section about thermal parameter and
Cross-section library is pre-machined by the way of piecewise interpolation and is used for heap core module for the variation of parameter preset, the parameter preset packet
It includes but is not limited to：Burnup, whether there is or not control rods.
Wherein, in the embodiment of the present application, the execution iteration coupling calculates until reactor core steady state power parameter and thermal technology
Parameter convergence specifically includes：
Start；
Input file is read, initialization component lacks group cross-section, reactor core neutron flux；
It carries out subchannel thermal technology's module stable state to calculate, group cross-section, reactor core neutron flux is lacked according to initial component, calculate reactor core
Interior moderator-density and coolant density distribution；
It is updated section, is distributed according to moderator-density and coolant density, interpolation calculation component lacks group cross-section；
It carries out three-dimensional neutronics module stable state to calculate, group cross-section is lacked according to new component, calculates and obtains component mean power
Distribution updates reactor core neutron flux；
It carries out subchannel thermal technology's module stable state to calculate, group cross-section, reactor core neutron flux is lacked according to new component, calculate reactor core
Interior moderator-density and coolant density distribution；
Judge whether power distribution restrains, if otherwise return to step re-starts update section；If then stable state calculates knot
Beam is calculated into transient state.
Wherein, in the embodiment of the present application, the supercritical water reactor reactor core Three dimensional transient physics-thermal-hydraulic coupling module
Transient state calculating is executed to specifically include：
Start transient state to calculate；
Time step update is carried out, the initial value at n moment is prepared；
It carries out subchannel thermal technology's module transient state and calculates a time step, group cross-section, core power point are lacked according to initial component
Cloth calculates heap in-core moderator-density and coolant density distribution；
It is updated section, is distributed according to moderator-density and coolant density, interpolation calculation component lacks group cross-section；
It carries out three-dimensional Neutron Time-Space Kinetics module transient state and calculates first time step, group cross-section is lacked according to new component,
It calculates and obtains core power distribution；
Judge whether power distribution restrains, executes time step update if otherwise returning, prepare the initial value at n moment；If then n
=n+1 judges that the n-th time step corresponds to whether time tn is less than preassigned transient state calculating time T, and the time is executed if then returning
Step update, prepares the initial value at n moment；Terminate if otherwise calculating.
Further, the supercritical water reactor reactor core three-dimensional steady state physics-thermal-hydraulic coupling module executes reactor core stable state
It calculates and the supercritical water reactor reactor core Three dimensional transient physics-thermal-hydraulic coupling module executes transient state and calculates, be all made of identical
Space method for solving：Second kind boundary condition locking nub green function method.In this way to ensure that three-dimensional steady state-transient state calculates analysis
The self-consistency of Neutronics calculation in the process.
Second kind boundary condition locking nub green function method solution throughway is as follows：
Three-dimensional Neutron Time-Space Kinetics equation form to be solved is：
Wherein, g characterizations energy group, energy group's sum are G；vgCharacterize g groups of neutron speeds, unit cms-1；Characterization
G groups of neutron flux, unit cm-2·s-1；DgCharacterize g group diffusion coefficients, unit cm；Σr,gAnd Σf,gG groups are characterized respectively
Removal cross-section and fission cross section, Σs,g′→gThe g ' groups are characterized to g groups of scattering sections, unit cm-1；χgCharacterization prompt neutron is split
Become spectrum；Fission discharges neutron population to ν characterizations every time；I characterizes delayed-neutron precursor grouping, and pioneer's core group sum is ND；χg,iCharacterization
I-th group of delayed neutron composes share；λiCharacterize i-th group of delayed-neutron precursor decay coefficient, unit s-1；Characterize i-th group
Delayed-neutron precursor concentration, unit cm-3；βiCharacterize i-th group of delayed neutron fraction.
To solve Transient Equations group (1), can rememberΔ t=t-
t0, y1=y (t), y0=y (t0), the wherein t characterizations current moment to be solved, t0Characterize last moment.F (t, y) characterizes equation group
(1) the several summation of non-temporal local derviation in, then equation group (1) can be abbreviated as：
The time discrete of equation stablizes Euler scheme backward using A-, can obtain：
y1=y0+Δt×f(t,y1) (3)
Using Euler scheme backward, pioneer's nuclear concentration equation is discrete to be：
Similarly, neutron flux equation is discrete is：
Formula (4), formula (5) are substituted into neutron diffusion equation, obtain formula (6), problem is converted into a fixed source problem：
Stationary source equation (6) is solved using the locking nub green function method based on second kind boundary condition, and solution throughway is such as
Under：
1, the Integral Solution that second kind boundary condition Green's function obtains laterally integrating inclined neutron flux equation is introduced；
2, it using the condition of continuity of locking nub interface non-homogeneous flux and stream, obtains interface and is averaged the corresponding square of net neutron current
Battle array；
3, inclined neutron flux, pioneer's nuclear concentration, transverse leakage item are all made of 2 rank Legendre polynomial expansions, using residue
The method of weighting solves inclined neutron flux expansion coefficient；
4, it solves locking nub neutron balance equation and obtains neutron average flux, and then correct inclined neutron flux expansion coefficient.
In locking nub Green's function solution procedure, reactor core is divided into the identical basic computational ele- ment of several nuclear cross sections, claims
Be locking nub.Using locking nub as the minimum unit of spatial spreading, k characterizes locking nub number, and the domain of x, y, the directions z coordinate are：
Illustrate by taking the directions x as an example.Along y, z both directions integrate formula (6) in locking nub k, you can obtain the inclined neutron in the directions x
Flux equation formula：
In formula,Characterize respectively lateral fluence, source item,
Fixed source item, transverse leakage item.
Green's function is introduced, then obtains the Integral Solution of inclined neutron flux equation：
In formula,Characterize the Green's function based on second kind boundary condition.
Non-homogeneous flux and net neutron current are continuous on adjacent locking nub interface.The non-homogeneous continuous expression formula of flux is：
Wherein,Characterize g group's discontinuous factors of the positive endpoint in k locking nub x coordinates direction.Characterize x coordinate direction k+1
The negative terminal discontinuous factor of locking nub.
Formula (9) is substituted into formula (10), while utilizing the net neutron current condition of continuity, can be obtained：
Formula (11) gives the net neutron current coupled relation on the internal interface of k locking nub x coordinates direction.In outer interface
Place, neutron current condition can be obtained by reactor core boundary condition, and then obtain the net neutron current response matrix of the row locking nub.With reactor core x
For the left margin of direction：
1, it by locking nub boundary reflective symmetry condition, can obtain：
2, it is 0 condition by incident flow, can obtains：
Formula (9) is substituted into formula (13), can be obtained：
3, it is 0 condition by boundary flux, can obtains：
Formula (9) is substituted into formula (15), can be obtained：
4, it by 90 ° of rotational symmetry conditions, can obtain：
Above-mentioned boundary condition is suitable for reactor core radial direction, can be by the directions reactor core x and the directions y locking nub Unified Solution.
Neutron balance equation can be by separately winning formula (6) volume in locking nub k：
In formula, u=x, y, z,Characterization locking nub volume-averaged flux, source item, fixation respectively
Source item.
Inclined neutron flux equation Integral Solution formula (9), net neutron current coupled relation formula (11) based on Green's function, based on section
The neutron balance equation formula (18) of block method constitutes skew integration Flux Distribution, interface net flow, the equation group of node average flux.
X is characterized with coordinate u, y, z coordinate, the one-dimensional abundance such as inclined flux, source, transverse leakage, can by 2 rank Legendre polynomial expansions
：
In formula：
(19) are substituted into formula (11) to formula (17), net flow response matrix can be obtained.Using Weighted residue method, it is logical to solve inclined neutron
Expansion coefficient is measured, weighting function is as shown in (20) formula.The matrix form that inclined neutron flux solves is：
In formula, underscore represents 3 dimensional vectors.Characterize expansion coefficient vector. WithIt can similarly obtain.WithIt characterizes respectivelyWithLegendre expansion
Coefficient；[Au] andFor 3 × 3 square formations, coefficient meets：
The expansion coefficient of transverse leakage item is solved using 2 rank approximation methods.Assuming that in adjacent 3 locking nubs, transverse leakage
N-th-trem relation n formula is set up, then 3 equations can be obtained by 3 locking nub average transverse leakages, to determine expansion coefficient.Coefficient expressions
For：
The average leaked of locking nub can be acquired by net neutron current：
The fundamental equation that locking nub Green's function transient state based on second kind boundary condition solves is by formula (11) to formula (17) group
At net flow response matrix, neutron balance equation formula (18) and inclined Flux Expansion coefficient equation (21) constitute, the source of can be used changes
It is solved for method.
Further, it is described execute reactor core Three dimensional transient physical computing three-dimensional Neutron Time-Space Kinetics module use when
Between discrete method be Euler's method backward.Wherein, Euler's method has absolutely-stability backward, and convenient for the serial of program
Coupling exploitation.
Wherein, using the instantaneous neutron calculation process of Euler's method backward, referring to FIG. 4, being specially：First in transformation
The correlative at one moment；It is ready for section；Then source item is updated；Then all directions interfaces is solved successively to be averaged net flow；Then
Solve node average flux and inclined neutron flux coefficient；Then judge whether all group energys meet the requirements, returned if being unsatisfactory for
Update source item is executed, if satisfied, then judging whether fission source restrains, if not restraining, execution update source item is returned to, if convergence
Update pioneer's nuclear concentration；Then subsequent time calculating is carried out.
The present invention is described in further detail with reference to the accompanying drawings and examples.
The present invention provides a kind of supercritical water reactor reactor core Three dimensional transient method for analyzing performance, using analysis of the present invention
The reactor core three-dimensional steady state of method-transient state physics-thermal-hydraulic couples calculation process as shown in Figure 1, using analysis of the present invention
The stable state calculation process of method is as shown in Fig. 2, using the transient state calculation process of analysis method of the present invention as shown in figure 3, figure
1, Fig. 2, Fig. 3 simply show a kind of embodiment that the present invention proposes concept, with reference to Fig. 1, Fig. 2, Fig. 3 and specific embodiment party
The invention will be further described for formula：
As shown in Figure 1, supercritical water reactor reactor core three-dimensional steady state-transient state physics-thermal-hydraulic coupling calculation process includes (1)
SCWR reactor cores three-dimensional steady state physics-thermal-hydraulic coupling calculates, (2) steady-state module is transmitted to transient state module data, (3) SCWR heaps
Core Three dimensional transient physics-thermal-hydraulic coupling calculating, (4) hot component subchannel thermal technology-water force, (5) key parameter safety
Evaluate five steps, wherein it includes in-core fuel management mould that SCWR reactor cores three-dimensional steady state physics-thermal-hydraulic coupling, which calculates (1),
Block calculates stable state reactor core and subchannel thermal technology-hydraulic module and calculates two parts of stable state reactor core, and steady-state module is to transient state number of modules
The data transmitted according to transmission (2) include initial core state and component cross-section library, SCWR reactor cores Three dimensional transient physics-thermal-hydraulic
It includes that three-dimensional Neutron Time-Space Kinetics module calculating transient state reactor core and subchannel thermal technology-hydraulic module calculate wink that coupling, which calculates (3),
Two parts of state reactor core, hot component subchannel thermal technology-water force (4) utilize thermal technology's module, the hot component after being reconstructed to power
It carries out subchannel and calculates analysis, provide maximum involucrum wall surface temperature (MCST), key parameter safety evaluation (5) is by judging MCST
Whether it is more than corresponding transient state or fail- safe limit value, security performance of the evaluation supercritical water reactor reactor core under transient process.
As shown in Fig. 2, in supercritical water reactor reactor core Three dimensional transient method for analyzing performance stable state calculation process, three-dimensional neutronics
Module and subchannel thermal technology module carry out reactor core stable state calculating respectively, and execute iteration coupling and calculate until power convergence.
As shown in figure 3, in supercritical water reactor reactor core Three dimensional transient method for analyzing performance transient state calculation process, subchannel thermal technology
Module and three-dimensional Neutron Time-Space Kinetics module carry out reactor core transient state calculating respectively, and execute iteration coupling and calculate until power is received
It holds back.
Above-mentioned supercritical water reactor reactor core Three dimensional transient method for analyzing performance, it is established that reactor core three-dimensional steady state-transient state physics-
Thermal-hydraulic couples calculation process, and it is three-dimensional to provide accurate reactor core for feedback that can be between accurate description physics and thermal technology-waterpower
Power is distributed, and realizes the purpose of the transient process and accident process of true simulation supercritical water reactor.
It gives a concrete illustration and is introduced below：
Using supercritical water reactor reactor core Three dimensional transient analysis method of the present invention, the hot zero power of supercritical water reactor is analyzed
Each transient problem under rate (HZP) and hot full power (HFP) state, to examine the applicability of Three dimensional transient analysis method.
Problem reactor core is supercritical water reactor CSR1000 reactor cores, under HZP and HFP states reactor core initial power be respectively 2300W and
2300MW.Transient problem is to play stick problem, and it is Section II flow component position E11 to play stick position.In HZP bullet stick problems, ejecting rod
Initial position is 7.7cm away from active region bottom, and bullet is to final position 420cm in 0.1s.In HFP bullet stick problems, at the beginning of ejecting rod
Beginning position is 210cm far from active region bottom, and bullet is to final position 420cm in 0.1s.The ejecting rod of HZP and HFP problems is worth
Respectively 683pcm and 293pcm.Using the Three dimensional transient analysis method, CSR1000 reactor core three-dimensional steady state objects are first carried out
Reason-thermal-hydraulic coupling module executes reactor core stable state and calculates, and in-core fuel management module is provided to subchannel thermal technology-hydraulic module
Power parameter, subchannel thermal technology-hydraulic module provide thermal parameter to in-core fuel management module, execute iteration coupling and calculate directly
It is restrained to reactor core steady state power parameter and thermal parameter；Then utilize reactor core three-dimensional steady state physics-thermal-hydraulic coupling module to
Reactor core Three dimensional transient physics-thermal-hydraulic coupling module provides reactor core original state and component cross-section library；Then CSR1000 is executed
Reactor core Three dimensional transient physics-thermal-hydraulic coupling module executes transient state and calculates, and three-dimensional Neutron Time-Space Kinetics module is to subchannel
Thermal technology-hydraulic module provides power parameter, and subchannel thermal technology-hydraulic module provides thermal technology to three-dimensional Neutron Time-Space Kinetics module
Parameter executes iteration coupling and calculates until reactor core transient power parameter and thermal parameter are restrained；Then to heat in reactor core calculating
Component carries out power and reconstructs to obtain the fine power distribution of hot component lattice cell scale, carries out hot component using thermal technology's module again
Multichannel analysis finally provides safety evaluation key parameter-maximum involucrum wall surface temperature；Finally judging maximum involucrum wall surface temperature is
No is more than fail- safe limit value, security performance of the evaluation CSR1000 reactor cores under rod ejection transient process.Three dimensional transient analysis result
Show that the reactor core peak power of HZP bullet stick problems is 0.68NP (rated power 2300MW), maximum involucrum wall surface temperature is 440
DEG C, less than 1260 DEG C of safety limit under accident conditions；The reactor core peak power of HFP bullet stick problems is 1.74NP, maximum involucrum wall
Face temperature is 1075 DEG C, less than 1260 DEG C of safety limit under accident conditions.To the Three dimensional transient point of CSR1000 reactor core bullet stick problems
Analysis shows either HFP bullets stick or HZP bullet sticks, and maximum involucrum wall surface temperature peak value is below fail- safe in accident process
1260 DEG C of limit value, meets safety requirements.
Technical solution in above-mentioned the embodiment of the present application, at least has the following technical effect that or advantage：
As a result of supercritical water reactor reactor core Three dimensional transient method for analyzing performance is designed as to include：Step 1：It is overcritical
Water-water reactor reactor core three-dimensional steady state physics-thermal-hydraulic coupling module executes reactor core stable state and calculates, and in-core fuel management module is logical to son
Road thermal technology-hydraulic module provides power parameter, and subchannel thermal technology-hydraulic module provides thermal technology's ginseng to in-core fuel management module
Number executes iteration coupling and calculates until reactor core steady state power parameter and thermal parameter are restrained；Step 2：Reactor core three-dimensional steady state physics-
Thermal-hydraulic coupling module provides reactor core original state to supercritical water reactor reactor core Three dimensional transient physics-thermal-hydraulic coupling module
With component cross-section library；Step 3：Supercritical water reactor reactor core Three dimensional transient physics-thermal-hydraulic coupling module executes transient state and calculates, and three
It ties up Neutron Time-Space Kinetics module and provides power parameter to subchannel thermal technology-hydraulic module, subchannel thermal technology-hydraulic module is to three
It ties up Neutron Time-Space Kinetics module and thermal parameter is provided, execute iteration coupling and calculate until reactor core transient power parameter and thermal technology join
Number convergence；Step 4：Power is carried out in reactor core calculating to hot component to reconstruct to obtain the fine power point of hot component lattice cell scale
Cloth carries out hot component subchannel analysis using thermal technology's module again, finally provides safety evaluation key parameter；Step 5：Judge institute
State whether safety evaluation key parameter is more than corresponding transient state or fail- safe limit value, evaluation supercritical water reactor reactor core is in transient state mistake
The technical solution of security performance under journey carries out transient state mistake by coupling three-dimensional Neutron Time-Space Kinetics with thermal technology-hydraulics
Journey is analyzed, and neutron dynamics part uses threedimensional model, so that it is had the three-dimensional power calculation ability of reactor core nuclear heat coupling, is realized super
The technique effect of critical water-water reactor reactor core Three dimensional transient analysis；So efficiently solving existing supercritical water reactor power distribution wink
State analysis method, which exists, does not have the three-dimensional power calculation ability of reactor core nuclear heat coupling, it is difficult to which true or accurate simulation is for example reacted
It the technical issues of transient process of property and power abnormal distribution event, realizes by establishing reactor core three-dimensional steady state-transient state physics-
Thermal-hydraulic couples calculation process, and feedback that can be between accurate description physics and thermal technology-waterpower provides more accurate reactor core three
Tie up power distribution, the technique effect of the transient process and accident process of true simulation supercritical water reactor.
Further, this method can true simulation supercritical water reactor reactor core transient process, improve to supercritical water reactor
The understanding of reactor core transient condition, more accurately estimation safety allowance, improvement Core Design simultaneously improve heap core performance.
Although preferred embodiments of the present invention have been described, it is created once a person skilled in the art knows basic
Property concept, then additional changes and modifications may be made to these embodiments.So it includes excellent that the following claims are intended to be interpreted as
It selects embodiment and falls into all change and modification of the scope of the invention.
Obviously, various changes and modifications can be made to the invention without departing from essence of the invention by those skilled in the art
God and range.In this way, if these modifications and changes of the present invention belongs to the range of the claims in the present invention and its equivalent technologies
Within, then the present invention is also intended to include these modifications and variations.
Claims (6)
1. a kind of supercritical water reactor reactor core Three dimensional transient method for analyzing performance, which is characterized in that the method includes：
Step 1：Supercritical water reactor reactor core three-dimensional steady state physics-thermal-hydraulic coupling module executes reactor core stable state and calculates, reactor core combustion
Expect that management module provides power parameter to subchannel thermal technology-hydraulic module, subchannel thermal technology-hydraulic module is to in-core fuel management
Module provides thermal parameter, executes iteration coupling and calculates until reactor core steady state power parameter and thermal parameter are restrained；
Step 2：Reactor core three-dimensional steady state physics-thermal-hydraulic coupling module is to supercritical water reactor reactor core Three dimensional transient physics-thermal technology
Seepage-stress coupling module provides reactor core original state and component cross-section library；
Step 3：Supercritical water reactor reactor core Three dimensional transient physics-thermal-hydraulic coupling module executes transient state and calculates, the period of the day from 11 p.m. to 1 a.m in three-dimensional
Lost motion mechanics module provides power parameter, subchannel thermal technology-hydraulic module period of the day from 11 p.m. to 1 a.m into three-dimensional to subchannel thermal technology-hydraulic module
Lost motion mechanics module provides thermal parameter, executes iteration coupling and calculates until reactor core transient power parameter and thermal parameter are restrained；
Step 4：Power is carried out in reactor core calculating to hot component to reconstruct to obtain the fine power distribution of hot component lattice cell scale, then
It is secondary to carry out hot component subchannel analysis using subchannel thermal technology-hydraulic module, finally provide safety evaluation key parameter；
Step 5：Judge whether the safety evaluation key parameter is more than corresponding transient state or fail- safe limit value, and evaluation is overcritical
Security performance of the water-water reactor reactor core under transient process；The safety evaluation key parameter includes：Maximum involucrum wall surface temperature, pellet
Heat content.
2. according to the method described in claim 1, it is characterized in that, making in the calculating of reactor core three-dimensional Neutron Time-Space Kinetics module
With few group cross-section, few group cross-section, which is pre-machined into about the variation of thermal parameter and parameter preset by the way of piecewise interpolation, to be cut
Face library is used for reactor core three-dimensional Neutron Time-Space Kinetics module, and the parameter preset includes：Fuel-assembly burn-up, whether there is or not controls
Stick.
3. according to the method described in claim 1, it is characterized in that, execution iteration coupling calculates until reactor core steady state power
Parameter and thermal parameter convergence specifically include：
Start；
Input file is read, initialization component lacks group cross-section, reactor core neutron flux；
Subchannel thermal technology-hydraulic module stable state is carried out to calculate；
It is updated section；
Three-dimensional Neutron Time-Space Kinetics module stable state is carried out to calculate；
Subchannel thermal technology's module stable state is carried out to calculate；
Judge whether core power distribution restrains, if otherwise return to step re-starts update section；If then stable state calculates knot
Beam is calculated into transient state.
4. according to the method described in claim 1, it is characterized in that, the supercritical water reactor reactor core Three dimensional transient physics-thermal technology
Seepage-stress coupling module executes transient state calculating and specifically includes：
Start transient state to calculate；
Time step update is carried out, the initial value at n moment is prepared；
It carries out subchannel thermal technology's module transient state and calculates a time step；
It is updated section；
It carries out three-dimensional Neutron Time-Space Kinetics module transient state and calculates first time step；
Judge whether core power distribution restrains, executes time step update if otherwise returning, prepare the initial value at n moment；If then n
=n+1；Judge whether tn is less than T, wherein tn is that the n-th time step corresponds to the time, when T is that preassigned transient state is calculated to T
It carves, executes time step update if then returning, prepare the initial value at n moment；Terminate if otherwise calculating.
5. according to the method described in claim 1, it is characterized in that, the supercritical water reactor reactor core three-dimensional steady state physics-thermal technology
Seepage-stress coupling module executes reactor core stable state and calculates and the supercritical water reactor reactor core Three dimensional transient physics-thermal-hydraulic coupling module
It executes transient state to calculate, is all made of identical space method for solving：Second kind boundary condition locking nub green function method.
6. according to the method described in claim 1, it is characterized in that, the time that the three-dimensional Neutron Time-Space Kinetics module uses
Discrete method is：Euler's method backward.
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