CN103617353A - Reactor simulation method, database processing method and reactor simulation system - Google Patents

Reactor simulation method, database processing method and reactor simulation system Download PDF

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CN103617353A
CN103617353A CN201310585269.6A CN201310585269A CN103617353A CN 103617353 A CN103617353 A CN 103617353A CN 201310585269 A CN201310585269 A CN 201310585269A CN 103617353 A CN103617353 A CN 103617353A
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group constant
few group
branch
database
primitive
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CN103617353B (en
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王苏
陈义学
余慧
李硕
刘志彦
孙业帅
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State Power Investment Group Science and Technology Research Institute Co Ltd
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China Nuclear (beijing) Science And Technology Research Institute Co Ltd
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Abstract

The invention discloses a reactor simulation method, a database processing method and a reactor simulation system. The reactor simulation method includes: dividing assembly group constant program computation branches to generate branch description information; according to the branch description information, computing assembly few-group constants for the branches one by one to obtain all basic data units of a few-group constant database; according to the branch description information, generating positioning information of each data unit in the few-group constant database; using the branch description information, the basic data units and the positioning information of each data unit to establish the few-group constant database; according to fuel loading assembly type, burnup level and operating conditions, reading data from the few-group constant database, processing to obtain matched few-group constants, and executing full-reactor-core simulation. By the scheme, efficiency of processing the few-group constant database by reactor core programs is improved and universal applicability to numerical simulation and computation of various nuclear fuel assemblies is guaranteed.

Description

Reactor analogy method, data base processing method and system
Technical field
The application relates to reactor physics numerical simulation field, particularly a kind of reactor analogy method, few group constant data base processing method and system.
Background technology
Assembly-reactor core two-step approach is a kind of technology path of reactor physics numerical simulation.Assembly-reactor core two-step approach guarantee model error in acceptable prerequisite lower compression nuclear reaction database can group, and only calculate relatively less geometric units in each step.And adopt full heap by the technology path of fuel rod numerical simulation, because of neutron energy group and geometric units, to divide number very large, caused that its efficiency cannot practical requirement under current engineering calculation hardware condition.Therefore, the commercial reactor physical quantity simulation package of international mainstream all adopts assembly-reactor core two-step mode technique route at present.
Few group constant database plays the effect of medium in assembly-reactor core two-step approach, has wherein stored the few group constant information of being calculated by component groups constant program under each discrete branch reference point.Traditional reactor core routine analyzer is the whole few group constant reference datas in pretreatment stage reading database first, then in the stage that solves according to simulated condition interpolation few group constant assignment to all basic geometric units-Jie pieces.In pressurized water reactor core analog computation, conventionally by following regular partition, save piece: in sagittal plane, do not divide or an assembly is divided into four parts; Axially take approximately 20 centimetres as one section of division.According to this current dividing mode, pressurized water reactor core will be divided into 4 * 10 3-3 * 10 4individual joint piece.Due to 1) joint piece division numbers is larger, and 2) may repeatedly upgrade all joint piece few group constants, 3 in once calculating) for each joint piece, compose few group constant value and consider again a plurality of reference factors, so conventionally comparatively consuming time to the processing of few group constant database.
US Westinghouse company has adopted the method for piecewise fitting few group constant database, a large amount of discrete of component groups constant program calculating is carried out to piecewise fitting with reference to few group constant, only fitting coefficient is deposited in to few group constant database.The advantage of processing has like this been greatly to reduce the volume of few group constant database, has promoted the efficiency of few group constant processing module in reactor core routine analyzer simultaneously.Yet the choosing and using corresponding to specific nuclear fuel assembly type of fitting function in this method, the assembly that constituent structure is differed greatly need to be chosen respectively, the precision of guarantee few group constant processing module.
Summary of the invention
The object of the invention is to improve the efficiency that reactor core routine analyzer is processed few group constant database, and guarantee that the present invention can have general applicability to the numerical simulation calculation of various nuclear fuel assemblies.
In one aspect of the invention, propose a kind of method that reactor is simulated, comprised step: according to predetermined configuration partitioning component group constant program Branch Computed, generated branch's descriptor; According to branch's descriptor Dui Ge branch computation module few group constant one by one, obtain whole primitives of few group constant database; According to branch's descriptor, generate the locating information of each data cell in few group constant database; Use the locating information of branch's descriptor, primitive and each data cell to set up few group constant database; And also process according to loading fuel assembly type, burn up level and operating condition reading out data in few group constant database the few group constant that obtains coupling, carry out full reactor core simulation.
In another aspect of this invention, propose a kind of few group constant database building method, having comprised: according to predetermined configuration partitioning component group constant program Branch Computed, generated branch's descriptor; According to branch's descriptor Dui Ge branch computation module few group constant one by one, obtain whole primitives of few group constant database; According to branch's descriptor, generate the locating information of each data cell in few group constant database; Use the locating information of branch's descriptor, primitive and each data cell to set up few group constant database.
Of the present invention, propose a kind of few group constant data and taken method more on the one hand, having comprised: obtain the essential information of few group constant database and open up data cached module: obtained the required primitive of interpolation joint piece few group constant; Interpolation calculation joint piece few group constant.
In still another aspect of the invention, propose a kind of system that reactor is simulated, having comprised: according to predetermined configuration partitioning component group constant program Branch Computed, generated the device of branch's descriptor; According to branch's descriptor Dui Ge branch computation module few group constant one by one, obtain the device of whole primitives of few group constant database; According to branch's descriptor, generate the device of the locating information of each data cell in few group constant database; The locating information of use branch descriptor, primitive and each data cell is set up the device of few group constant database; And also process according to loading fuel assembly type, burn up level and operating condition reading out data in few group constant database the few group constant that obtains coupling, carry out the device of full reactor core simulation.
In still another aspect of the invention, propose a kind of few group constant Database device, having comprised: according to predetermined configuration partitioning component group constant program Branch Computed, generated the device of branch's descriptor; According to branch's descriptor Dui Ge branch computation module few group constant one by one, obtain the device of whole primitives of few group constant database; According to branch's descriptor, generate the device of the locating information of each data cell in few group constant database; The locating information of use branch descriptor, primitive and each data cell is set up the device of few group constant database.
In still another aspect of the invention, proposed a kind of few group constant data taking device, having comprised: obtain the essential information of few group constant database and open up the device of data cached module: the device that obtains the required primitive of interpolation joint piece few group constant; The device of interpolation calculation joint piece few group constant.
From above technical scheme provided by the invention, in the present invention, few group constant data cell is carried out accurately operation and it is fully used, improved the efficiency of processing few group constant database, and the present invention, not for specific few group constant data mode, has general applicability to the various programming systems based on assembly-reactor core two-step approach.
The few group constant database that traditional components group constant program generates adopts the form of text formatting storage, reactor core routine analyzer needs to read whole few group constant database text file in use, and opens up redundancy memory space for storing a small amount of valid data and a large amount of this calculating without the data of calling.Valid data unit required in actual computation disperses random discontinuous position hereof, the present invention has added primitive locating information in few group constant database generative process, makes directly fast fetching valid data unit of reactor core routine analyzer.In addition, the present invention opens up special-purpose data cached module for storing the primitive having read in internal memory, when interpolation joint piece few group constant, if required data have read and have been stored in data cached module under judgement current working, no longer carry out and read few group constant database, but directly in data cached space, take desired data.This design can reduce the number of times of few group of group constant database reads extract operation, improves the execution efficiency of few group constant processing module.
The present invention does not change the form of traditional few group constant data cell, also without doing extra processing according to concrete nuclear reactor type or nuclear fuel assembly type, be that the method and actual numerical value problem of modelling are irrelevant, thereby the present invention can have general applicability to the numerical simulation calculation of various nuclear fuel assemblies.
Accompanying drawing explanation
In order to be illustrated more clearly in the embodiment of the present application or technical scheme of the prior art, to the accompanying drawing of required use in embodiment or description of the Prior Art be briefly described below, apparently, for those of ordinary skills, do not paying under the prerequisite of creative work, can also obtain according to these accompanying drawings other accompanying drawing.
Fig. 1 is the process flow diagram of method of the mock-up reactor of an embodiment of the application;
Fig. 2 is the process flow diagram of the method for setting up few group constant database of an embodiment of the application;
Fig. 3 is the process flow diagram that the few group constant data of an embodiment of the application are taken method;
Fig. 4 is the process flow diagram that the few group constant data of another embodiment of the application are taken method.
Embodiment
To describe specific embodiments of the invention in detail below, it should be noted that the embodiments described herein, only for illustrating, is not limited to the present invention.In the following description, in order to provide thorough understanding of the present invention, a large amount of specific detail have been set forth.Yet, for those of ordinary skills, it is evident that: needn't adopt these specific detail to carry out the present invention.In other examples, for fear of obscuring the present invention, do not specifically describe known structure, circuit, material or method.
In whole instructions, " embodiment ", " embodiment ", " example " or mentioning of " example " are meaned: special characteristic, structure or characteristic in conjunction with this embodiment or example description are comprised at least one embodiment of the present invention.Therefore phrase " in one embodiment ", " in an embodiment ", " example " or " example ", occurring in each place of whole instructions differs to establish a capital and refers to same embodiment or example.In addition, can with any suitable combination and/or sub-portfolio by specific feature, structure or property combination in one or more embodiment or example.In addition, it should be understood by one skilled in the art that term "and/or" used herein comprises any and all combinations of one or more relevant projects of listing.
Fig. 1 is the process flow diagram of method of the mock-up reactor of an embodiment of the application.In method as shown in Figure 1, use assembly-reactor core two step simulation processes, few group constant database is wherein to use the locating information of branch's descriptor, primitive and each data cell to set up, and has accelerated like this reading speed to data in few group constant database in simulation process.
In step 101, according to predetermined configuration partitioning component group constant program Branch Computed, generate branch's descriptor.
For example, the configuration of selecting according to user or the default configuration of system are carried out the division of assembly constant program branches.
The basic function of component groups constant program is to use multigroup constant storehouse to calculate to specify burn up level and burnup history, specify thermal-hydraulic operating condition, module diagnostic value and fundamental function under specified control rod insertion condition, and utilize multigroup neutron-flux density to calculate equivalent homogenization Few group parameter as weighting function.For guaranteeing that data in few group constant database can characterize any burn up level and burnup is historical, thermal-hydraulic operating condition and the few group constant under control rod insertion condition arbitrarily arbitrarily, need in database, store in a large number by component groups constant program in the basic few group constant data cell with reference to calculating under branch.
In the present embodiment user can be in input file specified rule or service routine default configuration rule choose and divide Branch Computed, for example, in certain particular problem, customer requirements comprises burn up level at few group constant database, fuel temperature, moderator temperature, boron concentration, control rod inserts the few group constant of branches of states, the 1000MWd/tU of take from 0MWd/tU divides 62 burnup points as interval, around moving 600 ℃ of average fuel temperature, get ± 50 ℃, ± 100 ℃ of totally 5 fuel temperature points, around moving 300 ℃ of average moderator temperature, get ± 20 ℃, ± 40 ℃ of totally 5 moderator temperature spots, the 100ppm of take from 0ppm divides 20 boron concentration point as interval, getting black rod inserts completely and inserts 2 control rods completely with grey rod and insert states.
With reference to branch's classification, can comprise: 1) characterize the nuclear fuel assembly equivalence burn up level of working time, 2) characterize the fuel temperature of nuclear fuel assembly instant operating condition level of living in, moderator temperature, coolant temperature, moderator density, coolant density, boron concentration etc., 3) control rod that characterizes automatic reaction compensation state of a control inserts state, 4) characterize the fuel temperature history of nuclear fuel assembly burnup history, moderator temperature history, coolant temperature is historical, moderator density is historical, coolant density is historical, boron concentration is historical, control rod inserts historical, power level history etc.
In the present embodiment, component groups constant program need generate basic few group constant data cell under each Branch Computed, the data category of this unit and storage rule are with concrete component groups constant program, and data category can comprise: the call parameter of homogenising macroscopic cross section, nucleic microscopic cross, nucleic decay rate, fission product yield, transient parameter, discontinuous factor, flux form factor and other analog computation nuclear fuel assembly operation characteristics.
In step 102, according to branch's descriptor Dui Ge branch computation module few group constant one by one, obtain whole primitives of few group constant database.
For example, according to neutron transportation theory, for each branch, according to multigroup nuclear reaction constant data storehouse, calculate the few group of the equivalent homogenization of each fuel assembly under various burn up level and operating condition nuclear reaction constant.
According to some embodiment, after dividing Branch Computed and definition data cell, 1) for the component groups constant program with branch's computing function, can be according to the whole branches of built-in regular cycle calculations of concrete component groups constant program, and result of calculation is treated to the form that meets primitive parameter classification and storage rule; 2), for the component groups constant program without branch's computing function, need calculate single branch according to user-defined regular recursive call component groups constant program, and result of calculation is treated to the form that meets primitive parameter classification and storage rule.
In step 103, according to branch's descriptor, generate the locating information of each data cell in few group constant database.
Because the number of the reference take-off point comprising in few group constant database calculates required primitive number much larger than a reactor core program, in real reaction heap numerical simulation calculation valid data unit be scattered in database in random site.For fear of traditional few group constant data method of taking, read the problem that whole database causes inefficiency, need be to reference to data generating positioning information in branch data unit and unit, to support capturing arbitrarily data in individual data unit or unit.
In the present embodiment, adopt two-level pointer location, first order pointer is for primitive is located, and second level pointer is for the single parameter location in primitive.Above pointer is used to indicate the relative physical location of object in computer-readable storage medium.
In step 104, use the locating information of branch's descriptor, primitive and each data cell to set up few group constant database.
For example the locating information of ,Jiang branch descriptor, primitive and each data cell writes the database that adopts layering one dimension binary format.Or the locating information of ,Jiang branch descriptor, primitive and each data cell writes the database that can directly operate random primitive.
The layering one dimension binary data base proposing in the present embodiment has following essential characteristic: the array of individual data and any dimension is all converted into one-dimension array, various data types are all stored with binary string, can be according to the position of arbitrary data section relative file head in computer-readable storage medium to arbitrary data section independent operation.
In the present embodiment, according to locating information, whole branches descriptor, primitive and data cell locating information are write to the database that adopts layering one dimension binary format, maybe the full detail except data cell location information is write to the database that other type can directly operate random primitive.
In step 105, according to loading fuel assembly type, burn up level and operating condition reading out data in few group constant database, also process the few group constant that obtains coupling, carry out full reactor core simulation.
For example, the three-dimensional reactor core routine analyzer based on neutron diffusion theory, also processes according to the nuclear fuel assembly type, burn up level and the operating condition that load reading out data in few group constant database the few group constant that obtains coupling, then carries out full reactor core analog computation.
Fig. 2 is the process flow diagram of the method for setting up few group constant database of an embodiment of the application.Described in the embodiment shown in Figure 2 and how to have set up above-mentioned few group constant database.
In step 201, according to predetermined configuration partitioning component group constant program Branch Computed, generate branch's descriptor.
For example, the configuration of selecting according to user or the default configuration of system are carried out the division of assembly constant program branches.
The basic function of component groups constant program is to use multigroup constant storehouse to calculate to specify burn up level and burnup history, specify thermal-hydraulic operating condition, module diagnostic value and fundamental function under specified control rod insertion condition, and utilize multigroup neutron-flux density to calculate equivalent homogenization Few group parameter as weighting function.For guaranteeing that data in few group constant database can characterize any burn up level and burnup is historical, thermal-hydraulic operating condition and the few group constant under control rod insertion condition arbitrarily arbitrarily, need in database, store in a large number by component groups constant program in the basic few group constant data cell with reference to calculating under branch.
In the present embodiment user can be in input file specified rule or service routine default configuration rule choose and divide Branch Computed, for example, in certain particular problem, customer requirements comprises burn up level at few group constant database, fuel temperature, moderator temperature, boron concentration, control rod inserts the few group constant of branches of states, the 1000MWd/tU of take from 0MWd/tU divides 62 burnup points as interval, around moving 600 ℃ of average fuel temperature, get ± 50 ℃, ± 100 ℃ of totally 5 fuel temperature points, around moving 300 ℃ of average moderator temperature, get ± 20 ℃, ± 40 ℃ of totally 5 moderator temperature spots, the 100ppm of take from 0ppm divides 20 boron concentration point as interval, getting black rod inserts completely and inserts 2 control rods completely with grey rod and insert states.
With reference to branch's classification, can comprise: 1) characterize the nuclear fuel assembly equivalence burn up level of working time, 2) characterize the fuel temperature of nuclear fuel assembly instant operating condition level of living in, moderator temperature, coolant temperature, moderator density, coolant density, boron concentration etc., 3) control rod that characterizes automatic reaction compensation state of a control inserts state, 4) characterize the fuel temperature history of nuclear fuel assembly burnup history, moderator temperature history, coolant temperature is historical, moderator density is historical, coolant density is historical, boron concentration is historical, control rod inserts historical, power level history etc.
In the present embodiment, component groups constant program need generate basic few group constant data cell under each Branch Computed, the data category of this unit and storage rule are with concrete component groups constant program, and data category can comprise: the call parameter of homogenising macroscopic cross section, nucleic microscopic cross, nucleic decay rate, fission product yield, transient parameter, discontinuous factor, flux form factor and other analog computation nuclear fuel assembly operation characteristics.
In step 202, according to branch's descriptor Dui Ge branch computation module few group constant one by one, obtain whole primitives of few group constant database.
For example, according to neutron transportation theory, for each branch, according to multigroup nuclear reaction constant data storehouse, calculate the few group of the equivalent homogenization of each fuel assembly under various burn up level and operating condition nuclear reaction constant.
According to some embodiment, after dividing Branch Computed and definition data cell, 1) for the component groups constant program with branch's computing function, can be according to the whole branches of built-in regular cycle calculations of concrete component groups constant program, and result of calculation is treated to the form that meets primitive parameter classification and storage rule; 2), for the component groups constant program without branch's computing function, need calculate single branch according to user-defined regular recursive call component groups constant program, and result of calculation is treated to the form that meets primitive parameter classification and storage rule.
In step 203, according to branch's descriptor, generate the locating information of each data cell in few group constant database.
Because the number of the reference take-off point comprising in few group constant database calculates required primitive number much larger than a reactor core program, in real reaction heap numerical simulation calculation valid data unit be scattered in database in random site.For fear of traditional few group constant data method of taking, read the problem that whole database causes inefficiency, need be to reference to data generating positioning information in branch data unit and unit, to support capturing arbitrarily data in individual data unit or unit.
In the present embodiment, adopt two-level pointer location, first order pointer is for primitive is located, and second level pointer is for the single parameter location in primitive.Above pointer is used to indicate the relative physical location of object in computer-readable storage medium.
In step 204, use the locating information of branch's descriptor, primitive and each data cell to set up few group constant database.
For example the locating information of ,Jiang branch descriptor, primitive and each data cell writes the database that adopts layering one dimension binary format.Or the locating information of ,Jiang branch descriptor, primitive and each data cell writes the database that can directly operate random primitive.
The layering one dimension binary data base proposing in the present embodiment has following essential characteristic: the array of individual data and any dimension is all converted into one-dimension array, various data types are all stored with binary string, can be according to the position of arbitrary data section relative file head in computer-readable storage medium to arbitrary data section independent operation.
In the present embodiment, according to locating information, whole branches descriptor, primitive and data cell locating information are write to the database that adopts layering one dimension binary format, maybe the full detail except data cell location information is write to the database that other type can directly operate random primitive.
In step 205, whether the database that judgement generates needs to do self check, if so, performs step 206, otherwise, complete the generation of database.
In step 206, in the database that sampling observation generates, whether discrete data can be treated as the acceptable joint piece of precision few group constant in reactor core routine analyzer.
When the variation tendency nonlinear degree of few group constant between two contiguous branch points is larger, the result of in this interval, designated state point being done to linear interpolation directly adopts substantial deviation the few group constant at component groups constant program calculation level place.
In the present embodiment, adopt arbitrary sampling method to choose one group of check point, the few group constant of linear interpolation check point, and the check point place few group constant comparison of calculating with invocation component group constant program, if detect the branching point that nonlinearity is larger, point out subscriber segmentation branch or segment branch according to built-in rule.
In step 207, judge whether database self-detection result can be accepted, and if so, completes the generation of database, otherwise, perform step 201 and repartition Branch Computed.
Fig. 3 is the process flow diagram that the few group constant data of an embodiment of the application are taken method.Referring to Fig. 3, for the application's few group constant data are taken the first embodiment process flow diagram of method:
In step 301, obtain the essential information of few group constant database, and open up data cached module.
In few group constant storehouse, except few group constant primitive, also comprise that database of descriptions branch classification is chosen branch's descriptor of dividing with take-off point and for locating the data cell locating information of data in primitive and unit.In the present embodiment, first read branch's descriptor and primitive locating information, and be that the information reading is opened up memory headroom.This step should be arranged at the pretreatment stage of core physics routine analyzer.
Data cached module described in the present embodiment refers to a storage space of opening up in calculator memory, is exclusively used in primitive and numbering thereof that storage has been read in.The elementary cell that the primitive of take in data cached module is opened up some as unit, this number can be specified by user, also can according to the calculating scale of reactor core numerical simulation, be calculated by program.
In step 302, obtain the required primitive of interpolation joint piece few group constant.
Joint piece is carried out before few group constant interpolation calculation, needed to obtain some few group constant data cells with reference to take-off point according to concrete interpolation method.Reactor core routine analyzer section by section piece interpolation is only used the part elementary cell in few group constant storehouse, and may be to some data cell Reusability.This is because in nuclear reactor actual motion and numerical simulation, and some nuclear fuel assemblies that each batch packs into are close at the burn up level of a certain time of running, entirely piles thermal-hydraulic parameter distribution also comparatively average.
In the present embodiment, first judge the primitive that whether comprises current retrieval in data cached module, if comprise, in data cached module, read in this data cell, otherwise in few group constant database, read in this data cell.
In step 303, interpolation calculation joint piece few group constant.
In the present embodiment, by the interpolation method arranging in concrete reactor core routine analyzer, adopt the primitive interpolation that step 302 is obtained to go out to specify the few group constant of joint piece under current operating condition.Often read a primitive in few group constant storehouse, all need to store into data cached module.Primitive is being deposited in before data cached module, needing the rule numbers by concrete reactor core routine analyzer, and setting up the mapping relations of memory location in numbering and data cached module.Deposit in the lump data cell and corresponding numbering in data cached module.
Fig. 4 is the process flow diagram that the few group constant data of another embodiment of the application are taken method.Referring to Fig. 4, for the application's few group constant data are taken the second embodiment process flow diagram of method:
In step 401, read branch's descriptor and primitive locating information in few group constant database.
In few group constant storehouse, except few group constant primitive, also comprise that database of descriptions branch classification is chosen branch's descriptor of dividing with take-off point and for locating the data cell locating information of data in primitive and unit.
In the present embodiment, first read branch's descriptor and primitive locating information, and be that the information reading is opened up memory headroom.This step should be arranged at the pretreatment stage of core physics routine analyzer.
In step 402, in internal memory, to open up and take the data cached module that primitive is unit, the number of initial buffer unit is specified by user or calculates according to few group constant storehouse branch descriptor.
Data cached module described in the present embodiment refers to a storage space of opening up in calculator memory, is exclusively used in primitive and numbering thereof that storage has been read in.The elementary cell that the primitive of take in data cached module is opened up some as unit, this number can be specified by user, also can according to the calculating scale of reactor core numerical simulation, be calculated by program.
In step 403, calculate interpolation when the required whole primitive numberings of prosthomere piece few group constant.
In the present embodiment, according to the coding rule of the operating condition of each joint piece and concrete reactor core routine analyzer, calculate the required primitive numbering of this joint piece of assignment.
In step 404, judge the primitive numbering that whether comprises current retrieval in data cached module, if so, perform step 405, otherwise, perform step 406.
In step 405, from data cached module, read required primitive.
In the present embodiment, according to the mapping relations of data cell memory location in data cell numbering and data cached module, in data cached module, read in few group constant data cell.
In step 406, from few group constant database, read required primitive.
In the present embodiment, according to primitive locating information, in few group constant database, read in few group constant data cell.
In step 407, whether the data cached module space that judgement has been opened up is write full, if so, performs step 408, otherwise, perform step 409.
In step 408, append and open up buffer unit.
If occur in the present embodiment, in data cached module, opened up the situation that buffer unit is used up, according to the number of user's appointment or according to calculating scale calculate number append and open up.
In step 409, the data cell reading in step 406 and numbering are write to data cached module
In the present embodiment, often read a primitive in few group constant storehouse, all need to store into data cached module.Primitive is being deposited in before data cached module, needing the rule numbers by concrete reactor core routine analyzer, and setting up the mapping relations of memory location in numbering and data cached module.This step deposits data cell and corresponding numbering in data cached module in the lump.
In step 410, judge whether to obtain the required data cell of whole interpolation, if so, perform step 411, otherwise, return to step 404.
In step 411, when obtaining interpolation after the required whole primitives of prosthomere piece few group constant, carry out interpolation operation and compose few group constant for saving piece.
In the present embodiment, by the interpolation method arranging in concrete reactor core routine analyzer, adopt the primitive interpolation that step 203-210 obtains to go out to specify the few group constant of joint piece under current operating condition.
In step 412, judge whether for all saving piece, to compose few group constant, if so, complete few group constant data to take, otherwise, return to step 403.
Above detailed description, by using schematic diagram and/or example, has been set forth numerous embodiment of the method and system of monitoring reactor core power.In the situation that this schematic diagram and/or example comprise one or more functions and/or operation, it will be understood by those skilled in the art that each function in this example and/or operation can by various hardware, software, firmware or in fact their combination in any come separately and/or jointly realize.In one embodiment, described in embodiments of the invention, some parts of theme can realize by special IC (ASIC), field programmable gate array (FPGA), digital signal processor (DSP) or other integrated forms.Yet, those skilled in the art will recognize that, some aspects of embodiment disclosed herein can realize in integrated circuit on the whole or partly equally, (be for example embodied as one or more computer programs of moving on one or more computing machine, be embodied as one or more programs of moving in one or more computer system), (be for example embodied as one or more programs of moving on one or more processors, be embodied as one or more programs of moving on one or more microprocessors), be embodied as firmware, or be embodied as in fact the combination in any of aforesaid way, and those skilled in the art are according to the disclosure, to possess design circuit and/or write software and/or the ability of firmware code.In addition, those skilled in the art will recognize that, described in the disclosure, the mechanism of theme can be distributed as the program product of various ways, and regardless of the actual particular type that is used for carrying out the signal bearing medium of distribution, and the exemplary embodiment of theme is all applicable described in the disclosure.The example of signal bearing medium includes but not limited to: recordable-type media, as floppy disk, hard disk drive, compact-disc (CD), digital universal disc (DVD), numerical tape, computer memory etc.; And transmission type media, for example, as numeral and/or analogue communication medium (, optical fiber cable, waveguide, wire communication link, wireless communication link etc.).
Although described the present invention with reference to several exemplary embodiments, should be appreciated that term used is explanation and exemplary and nonrestrictive term.The spirit or the essence that because the present invention can specifically implement in a variety of forms, do not depart from invention, so be to be understood that, above-described embodiment is not limited to any aforesaid details, and explain widely in the spirit and scope that should limit in the claim of enclosing, therefore fall into whole variations in claim or its equivalent scope and remodeling and all should be the claim of enclosing and contain.

Claims (18)

1. a method of reactor being simulated, comprises step:
According to predetermined configuration partitioning component group constant program Branch Computed, generate branch's descriptor;
According to branch's descriptor Dui Ge branch computation module few group constant one by one, obtain whole primitives of few group constant database;
According to branch's descriptor, generate the locating information of each data cell in few group constant database;
Use the locating information of branch's descriptor, primitive and each data cell to set up few group constant database; And
According to loading fuel assembly type, burn up level and operating condition reading out data in few group constant database, also process the few group constant that obtains coupling, carry out full reactor core simulation.
2. the method for claim 1, wherein according to branch's descriptor one by one the step of Dui Ge branch computation module few group constant comprise:
For each branch, according to multigroup nuclear reaction constant data storehouse, calculate the few group of the equivalent homogenization of each fuel assembly under various burn up level and operating condition nuclear reaction constant.
3. the method for claim 1, wherein writes the locating information of branch's descriptor, primitive and each data cell the database that adopts layering one dimension binary format.
4. the method for claim 1 device, wherein writes the locating information of branch's descriptor, primitive and each data cell the database that can directly operate random primitive.
5. the method for claim 1, wherein in few group constant database, reading out data the step of processing the few group constant that obtains coupling comprise:
Obtain the essential information of few group constant database and open up data cached module:
Obtain the required primitive of interpolation joint piece few group constant;
Interpolation calculation joint piece few group constant.
6. method as claimed in claim 5, the step of wherein obtaining the essential information of few group constant database and opening up data cached module comprises:
Read branch's descriptor and primitive locating information in few group constant database;
In internal memory, open up and take the data cached module that primitive is unit, the number of initial buffer unit is specified by user or calculates according to few group constant storehouse branch descriptor.
7. method as claimed in claim 5, the step of wherein obtaining the required primitive of interpolation joint piece few group constant comprises:
Calculate interpolation when the required whole primitive numberings of prosthomere piece few group constant;
Mate one by one the element number of having deposited in data cached module, judge whether the required primitive of interpolation has read in data cached module;
If read in data cached module, from data cached module, read required primitive;
If do not read in data cached module, from few group constant database, read required primitive, and this data cell and numbering are write to data cached module.
8. method as claimed in claim 5, the step of wherein said interpolation calculation joint piece few group constant comprises:
When obtaining interpolation after the required whole primitives of prosthomere piece few group constant, carry out interpolation operation and compose few group constant for saving piece;
After completing whole appointment joint piece assignment, complete taking of few group constant data.
9. a few group constant database building method, comprising:
According to predetermined configuration partitioning component group constant program Branch Computed, generate branch's descriptor;
According to branch's descriptor Dui Ge branch computation module few group constant one by one, obtain whole primitives of few group constant database;
According to branch's descriptor, generate the locating information of each data cell in few group constant database;
Use the locating information of branch's descriptor, primitive and each data cell to set up few group constant database.
10. method as claimed in claim 9, wherein writes the locating information of branch's descriptor, primitive and each data cell the database that adopts layering one dimension binary format.
11. methods as claimed in claim 9, wherein write the locating information of branch's descriptor, primitive and each data cell the database that can directly operate random primitive.
12. 1 kinds of few group constant data are taken method, comprising:
Obtain the essential information of few group constant database and open up data cached module:
Obtain the required primitive of interpolation joint piece few group constant;
Interpolation calculation joint piece few group constant.
13. methods as claimed in claim 12, the step of wherein obtaining the essential information of few group constant database and opening up data cached module comprises:
Read branch's descriptor in few group constant database and the locating information of primitive;
In internal memory, open up and take the data cached module that primitive is unit, the number of initial buffer unit is specified by user or calculates according to few group constant storehouse branch descriptor.
14. methods as claimed in claim 12, the step of wherein obtaining the required primitive of interpolation joint piece few group constant comprises:
Calculate interpolation when the required whole primitive numberings of prosthomere piece few group constant;
Mate one by one the element number of having deposited in data cached module, judge whether the required primitive of interpolation has read in data cached module;
If read in data cached module, from data cached module, read required primitive;
If do not read in data cached module, from few group constant database, read required primitive, and this data cell and numbering are write to data cached module.
15. methods as claimed in claim 12, the step of wherein said interpolation calculation joint piece few group constant comprises:
When obtaining interpolation after the required whole primitives of prosthomere piece few group constant, carry out interpolation operation and compose few group constant for saving piece;
After completing whole appointment joint piece assignment, complete taking of few group constant data.
16. 1 kinds of systems that reactor is simulated, comprising:
According to predetermined configuration partitioning component group constant program Branch Computed, generate the device of branch's descriptor;
According to branch's descriptor Dui Ge branch computation module few group constant one by one, obtain the device of whole primitives of few group constant database;
According to branch's descriptor, generate the device of the locating information of each data cell in few group constant database;
The locating information of use branch descriptor, primitive and each data cell is set up the device of few group constant database; And
According to loading fuel assembly type, burn up level and operating condition reading out data in few group constant database, also process the few group constant that obtains coupling, carry out the device of full reactor core simulation.
17. 1 kinds of few group constant Database devices, comprising:
According to predetermined configuration partitioning component group constant program Branch Computed, generate the device of branch's descriptor;
According to branch's descriptor Dui Ge branch computation module few group constant one by one, obtain the device of whole primitives of few group constant database;
According to branch's descriptor, generate the device of the locating information of each data cell in few group constant database;
The locating information of use branch descriptor, primitive and each data cell is set up the device of few group constant database.
18. 1 kinds of few group constant data taking devices, comprising:
Obtain the essential information of few group constant database and open up the device of data cached module:
Obtain the device of the required primitive of interpolation joint piece few group constant;
The device of interpolation calculation joint piece few group constant.
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CN106886686A (en) * 2017-03-03 2017-06-23 西安交通大学 A kind of compound modification method of presurized water reactor few group constant history effect
CN106886686B (en) * 2017-03-03 2019-02-26 西安交通大学 A kind of compound modification method of presurized water reactor few group constant history effect
CN107122564A (en) * 2017-05-12 2017-09-01 西安交通大学 A kind of presurized water reactor pin by pin calculate few group constant parametric method
CN107122564B (en) * 2017-05-12 2020-01-24 西安交通大学 Parameterization method for calculating few group constants of pin-by-pin of pressurized water reactor
CN110110340A (en) * 2018-02-01 2019-08-09 国家电投集团科学技术研究院有限公司 The tracking and system of reactor three-dimensional micromodule information
CN112632771A (en) * 2020-12-21 2021-04-09 中国核动力研究设计院 Method and equipment for solving response sensitivity of fuel consumption calculation
CN114528719A (en) * 2022-04-22 2022-05-24 西安交通大学 Online energy group compression method for pressurized water reactor based on two-dimensional reactor core
CN114528719B (en) * 2022-04-22 2022-07-08 西安交通大学 Online energy group compression method for pressurized water reactor based on two-dimensional reactor core

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