CN108806810A - Nuclear fuel rod method for analyzing performance - Google Patents
Nuclear fuel rod method for analyzing performance Download PDFInfo
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- CN108806810A CN108806810A CN201810622867.9A CN201810622867A CN108806810A CN 108806810 A CN108806810 A CN 108806810A CN 201810622867 A CN201810622867 A CN 201810622867A CN 108806810 A CN108806810 A CN 108806810A
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/001—Mechanical simulators
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- Y—GENERAL TAGGING OF NEW TECHNOLOGICAL DEVELOPMENTS; GENERAL TAGGING OF CROSS-SECTIONAL TECHNOLOGIES SPANNING OVER SEVERAL SECTIONS OF THE IPC; TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
- Y02—TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
- Y02E—REDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
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Abstract
The invention discloses a kind of nuclear fuel rod method for analyzing performance.Wherein, this method includes：Obtain the information of multiple axial direction parts, wherein axial direction part is that single nuclear fuel rod is prolonged one section of fuel rod that axial segmentation is formed；The information of multiple axial direction parts is distributed into multiple processes, wherein each process at least distributes the information of an axial direction part；The performance of multiple axial direction parts is analyzed in the process that the information of axial direction part is distributed；The performance of single nuclear fuel rod is obtained according to the performance of multiple axial direction parts).The present invention solves the technical problem slower to single rod analyze speed existing in the prior art.
Description
Technical field
The present invention relates to fuel element performance evaluation fields, in particular to a kind of nuclear fuel rod method for analyzing performance.
Background technology
Fuel element (nuclear fuel rod) is the core component of nuclear reactor, can be rated as " heart " of reactor, is reactor fortune
Heat is generated during row and maintains the main source of chain reaction.The performance of nuclear fuel element and component to the phase in reactor longevity,
Safety and economy have far-reaching influence, so working performance and longevity of the performance evaluation of fuel element to nuclear reactor
Life, it is also particularly significant to the analysis of the design and operation of reactor and safety.
The prior art to the analysis of fuel element performance primarily directed to single fuel element, for example, being managed by U.S.'s core
Method (the FRAPCON- for the steady-state response of light-water reactor fuel rod when calculating long-term burnup of the committee (NRC) exploitation
3).This method is as unit of the time, and rod power and coolant liquid boundary condition are input, according to the specified time step of input
The time is promoted, steady-state solution is executed, determines new fuel rod state.The temperature of fuel and involucrum is calculated in each time step
Degree, the deformation for calculating fuel and involucrum, the generation for calculating fission product and release calculate voidage, calculate inside fuel rod
Pressure etc. simulates a series of phenomenons under fuel rod stable situation：1) by fuel and covering to the heat transfer of coolant；
2) covering elasticity and plasticity deforms；3) fuel covering mechanical interaction；4) fission gas releases stress inside fuel and stick；
5) covering oxidation etc..
The above method can calculate the performance of single light-water reactor fuel rod, but cannot be to multiple fuel rods simultaneously
Performance evaluation is carried out to Whole core fuel rod；Meanwhile if existing method individually will be directly subjected to easy parallel malfunction, simultaneously
Row difficulty is larger.In addition to this, the speed of the single rod analysis of the prior art is slower.
Cannot analysis be carried out to more sticks simultaneously present in for the above-mentioned prior art and single rod analyze speed is slower
Problem, currently no effective solution has been proposed.
Invention content
An embodiment of the present invention provides a kind of nuclear fuel rod method for analyzing performance, existing in the prior art at least to solve
The technical problem slower to single rod analyze speed.
One side according to the ... of the embodiment of the present invention provides a kind of single nuclear fuel rod method for analyzing performance, including：It obtains
Take the information of multiple axial direction parts, wherein the axial direction part is that single nuclear fuel rod is prolonged one section of fuel rod that axial segmentation is formed；
The information of multiple axial direction parts is distributed into multiple processes, wherein each process at least distributes the information of an axial direction part；?
The performance of multiple axial direction parts is analyzed in the process that the information of the axial direction part is distributed；Institute is obtained according to the performance of multiple axial direction parts
State the performance of single nuclear fuel rod.
Further, the information of multiple axial direction parts is distributed to multiple processes includes：By the information of the multiple axial direction part
Distribute to multiple processes, wherein the information of the axial direction part of each course allocation predetermined number, the total quantity of the axial direction part are more than
Equal to the total quantity of the process；According to the information of the analyze speed of each process remaining axial direction part of sub-distribution again.
Further, include according to the information of the analyze speed of each process remaining axial direction part of sub-distribution again：Judge every
The speed speed of axial direction part described in a process analysis；Priority ranking is carried out to process according to the speed speed；According to preferential
Grade height distributes remaining axial direction part.
Further, the performance of the axial direction part includes：Temperature, ess-strain, internal pressure, involucrum corrosion.
One side according to the ... of the embodiment of the present invention provides a kind of multiple nuclear fuel rod method for analyzing performance, including：It obtains
Take the information of multiple nuclear fuel rods；The information of the multiple nuclear fuel rod is distributed to multiple processes, wherein in multiple processes
Each process corresponds to the information of a nuclear fuel rod, and the quantity of the process is identical as the quantity of the nuclear fuel rod；According to institute
The information of nuclear fuel rod is stated in multiple processes while analyzing the performance of multiple nuclear fuel rods.
One side according to the ... of the embodiment of the present invention provides a kind of single nuclear fuel rod performance evaluation device, including：It obtains
Modulus block, the information for obtaining multiple axial direction parts, wherein the axial direction part is that single nuclear fuel rod is prolonged axial segmentation to be formed
One section of fuel rod；Distribution module, for the information of multiple axial direction parts to be distributed to multiple processes, wherein each process is at least
Distribute the information of an axial direction part；First analysis module, for dividing in the process that the information of the axial direction part is distributed
Analyse the performance of multiple axial direction parts；Second analysis module, for obtaining the single nuclear fuel rod according to the performance of multiple axial direction parts
Performance.
Further, the distribution module includes：First distribution sub module, for dividing the information of the multiple axial direction part
The multiple processes of dispensing, wherein the information of the axial direction part of each course allocation predetermined number, the total quantity of the axial direction part are more than etc.
In the total quantity of the process；Second distribution sub module, for according to the analyze speed of each process remaining institute of sub-distribution again
State the information of axial direction part.
Further, second distribution sub module includes：Judging submodule, for judging axis described in each process analysis
To the speed speed of section；Sorting sub-module, for carrying out priority ranking to process according to the speed speed；Distribute submodule
Block, for distributing remaining axial direction part according to priority height.
One side according to the ... of the embodiment of the present invention provides a kind of multiple nuclear fuel rod performance analysis systems, including：It obtains
Unit is taken, the information for obtaining multiple nuclear fuel rods；Dispatching Unit, for the information of the multiple nuclear fuel rod to be distributed to
Multiple processes, wherein each process in multiple processes corresponds to the information of a nuclear fuel rod, the quantity of the process with it is described
The quantity of nuclear fuel rod is identical；Analytic unit, for analysis to be more simultaneously in multiple processes according to the information of the nuclear fuel rod
The performance of a nuclear fuel rod.
Other side according to the ... of the embodiment of the present invention has been also provided to a kind of storage medium, has been protected on the storage medium
Computer program stored executes the upper method when described program is run.
Other side according to the ... of the embodiment of the present invention has been also provided to a kind of processor, has been held when described program is run
The above-mentioned method of row.
In embodiments of the present invention, using the information for obtaining multiple axial direction parts, wherein the axial direction part is to fire single core
Charge bar prolongs one section of fuel rod that axial segmentation is formed；The information of multiple axial direction parts is distributed into multiple processes, wherein each process
At least distribute the information of an axial direction part；Multiple axial direction parts are analyzed in the process that the information of the axial direction part is distributed
Performance；The mode of the performance of the single nuclear fuel rod is obtained according to the performance of multiple axial direction parts, and then solves the prior art
Present in the technical problem slower to single rod analyze speed improve analysis to largely shorten analysis time
Efficiency.
Description of the drawings
Attached drawing described herein is used to provide further understanding of the present invention, and is constituted part of this application, this hair
Bright illustrative embodiments and their description are not constituted improper limitations of the present invention for explaining the present invention.In the accompanying drawings：
Fig. 1 is a kind of schematic diagram of single nuclear fuel rod method for analyzing performance according to the ... of the embodiment of the present invention；
Fig. 2 is a kind of axially and radially radial node division signal of single nuclear fuel rod according to the ... of the embodiment of the present invention
Figure；
Fig. 3 is that have the schematic diagram for influencing each other and coupling between a kind of single rod analysis module according to the ... of the embodiment of the present invention；
Fig. 4 is a kind of analysis process figure of single nuclear fuel rod according to the ... of the embodiment of the present invention；
Fig. 5 is process and task allocation result schematic diagram in a kind of optional single rod according to the ... of the embodiment of the present invention；
Fig. 6 is process and task allocation result schematic diagram in another optional single rod according to the ... of the embodiment of the present invention；
Fig. 7 is a kind of schematic diagram of multiple nuclear fuel rod parallel parsings according to the ... of the embodiment of the present invention；
Fig. 8 is that a kind of thermal module according to the ... of the embodiment of the present invention solves flow chart；
Fig. 9 is a kind of schematic diagram of single nuclear fuel rod performance evaluation device according to the ... of the embodiment of the present invention.
Specific implementation mode
In order to enable those skilled in the art to better understand the solution of the present invention, below in conjunction in the embodiment of the present invention
Attached drawing, technical scheme in the embodiment of the invention is clearly and completely described, it is clear that described embodiment is only
The embodiment of a part of the invention, instead of all the embodiments.Based on the embodiments of the present invention, ordinary skill people
The every other embodiment that member is obtained without making creative work should all belong to the model that the present invention protects
It encloses.
It should be noted that term " first " in description and claims of this specification and above-mentioned attached drawing, "
Two " etc. be for distinguishing similar object, without being used to describe specific sequence or precedence.It should be appreciated that using in this way
Data can be interchanged in the appropriate case, so as to the embodiment of the present invention described herein can in addition to illustrating herein or
Sequence other than those of description is implemented.In addition, term " comprising " and " having " and their any deformation, it is intended that cover
It includes to be not necessarily limited to for example, containing the process of series of steps or unit, method, system, product or equipment to cover non-exclusive
Those of clearly list step or unit, but may include not listing clearly or for these processes, method, product
Or the other steps or unit that equipment is intrinsic.
According to embodiments of the present invention, a kind of single nuclear fuel rod method for analyzing performance embodiment is provided, needs to illustrate
It is that step shown in the flowchart of the accompanying drawings can execute in the computer system of such as a group of computer-executable instructions,
Also, although logical order is shown in flow charts, and it in some cases, can be to be executed different from sequence herein
Shown or described step.
Fig. 1 is single nuclear fuel rod method for analyzing performance according to the ... of the embodiment of the present invention, as shown in Figure 1, this method includes
Following steps：
Step S102 obtains the information of multiple axial direction parts, wherein axial direction part is that single nuclear fuel rod is prolonged axial segmentation shape
At one section of fuel rod；
The information of multiple axial direction parts is distributed to multiple processes by step S104, wherein each process at least distributes an axis
To the information of section；
Step S106 analyzes the performance of multiple axial direction parts in the process distributed of information of axial direction part；
Step S108 obtains the performance of single nuclear fuel rod according to the performance of multiple axial direction parts.
Influence between above-mentioned steps negligible axial section, therefore to axial direction part Parallel implementation.
The information of above-mentioned axial direction part be can weigh the input information of some axial direction part performance, that is, with temperature, stress
The corresponding input informations such as strain, internal pressure, involucrum corrosion.For example, distribution of the temperature on pellet and involucrum is the core of input
The information of axial direction part, the corresponding temperature exported represent the performance of core axial direction part.The input information for influencing temperature performance is also wrapped
Include the parameters such as the ring diameter of axial direction part, involucrum internal-and external diameter, gap heat transfer coefficient, pellet thermal conductivity.The corresponding axial direction part of ess-strain
Information refer to the parameters such as elasticity modulus, modulus of shearing, Poisson's ratio；The information of the corresponding axial direction part of internal pressure refers to temperature, transmitting
The parameters such as rate；The information that involucrum corrodes corresponding axial direction part refers to the parameters such as fusing point, phase transformation.
Single nuclear fuel rod is split into multiple axial direction parts (as shown in Figure 2) through the above steps, to each axial direction part
Performance is carried out at the same time analysis respectively, this be only that carry out analysis to whole complete single nuclear fuel rod be not in the prior art
Together, the parallel parsing in nuclear fuel rod may be implemented, the correlation of the multistage fuel rod in the same fuel rod can be solved simultaneously
Physical quantity；Largely shorten and solve the time, improves solution efficiency.
In above-mentioned steps, using the process of each axial direction part of each process analysis, it is equivalent to an individual processor
It goes to analyze each axial direction part, used analysis method can be the analysis method of whole single nuclear fuel rod.
By carrying out calculating demand analysis and functional requirement analysis to fuel element Performance Analysis Software, as shown in figure 3, point
6 function modules can be divided by analysing the software of single nuclear fuel rod：Neutronics module, thermal module, mechanics module, fission
Gas release module, interior die block, involucrum corrode module；It influences each other and couples between analysis module；It is final to realize single rod
The parallel parsing of energy analysis and Whole core Most spent fuel rod.
The function of modules is as follows：Neutronics functions of modules：Calculate fuel pellet internal power density, Nuclear analysis
Deng, for Temperature Distribution calculating power parameter is provided.Thermal module function：Heat is finally passed by gap, involucrum in simulation pellet
The process for entering coolant calculates fuel element temperature distribution according to coolant boundary condition and rod power history.Mechanics mould
Block feature capability：Task is the stress for calculating involucrum, strain.It can analyze whether involucrum fails according to involucrum stress, strain.Fission
Gas release module：It is mainly simulated in intracell diffusion process by single gas atom, calculates gas burst size.It is interior
Die block function：Calculate the internal pressure of fuel rod.Involucrum corrodes functions of modules：Zirconium alloy cladding is calculated in high temperature coolant to occur
The thickness for the oxidation film that metal-water exothermic reaction generates.
Analysis process to single fuel rod is also the analysis done to each axial direction part in above-mentioned steps (software is serial)
As shown in figure 4, specific as follows：
1. initializing input data
2. starting outermost layer time step cycle, data update in time step
3. starting second layer air pressure iteration, start third layer axial node cycle
4. axial layer data update
5. pellet relocates
6. starting gap conductance iteration
7. calculating fuel rod temperature (thermal module)
8. calculating fuel and involucrum deformation (mechanics module)
9. judging whether the gap temperature difference restrains
A) no, return to F
B) it is that gap conductance iteration terminates
10. calculating fission gas burst size, voidage (fission gas release module)
11. calculating fuel rod pressure (interior die block)
12. after completing to the calculating of whole axial nodes, exiting axial node cycle
13. judging whether air pressure iteration restrains
A) no, return to C
B) it is that air pressure iteration terminates
14. calculating involucrum extent of corrosion (involucrum corrosion module)
15. time step controls
16. EP (end of program).
The information of multiple axial direction parts is distributed into multiple processes in above-mentioned steps, can be that a process handles multiple axial directions
Section, can also be that a process only handles an axis phase section, in an optional embodiment, first, by multiple axial direction parts
Information distribute to multiple processes, wherein the information of the axial direction part of each course allocation predetermined number, the total quantity of axial direction part are big
In the total quantity equal to process；Then, according to the information of the analyze speed of each process remaining axial direction part of sub-distribution again.
The above process is illustrated below according to an optional embodiment citing：
Above-mentioned steps can recycle to execute the performance evaluation of axial direction part each time using for, and the cycle each time of for is just
To calculate an axial direction part, the above process is the dynamic dispatching to axial direction part, dynamic dispatching refer to dynamically by each for repeatedly
In generation, is assigned on each thread, and each iteration, which represents, calculates an axial direction part, for example, 10 for cycles represent and calculate 10
Axial direction part；The predetermined number of the axial direction part of above-mentioned predetermined number indicated using size in the present embodiment, the size of each size
Also representative for cycle assignments will give each process (thread), the predetermined number (size) of the axial direction part of each predetermined number several times
At least one, size parameters can be used, size parameters, in the case of not using size parameters, size values can not also be used
It is defaulted as 1, each size can be used as a subtask, above-mentioned steps that dynamically subtask is assigned on each thread, point
Timing can distribute to each thread based on prerequisite variable mode.It, can also be according to each when distributing subtask to thread
The performance of thread reallocates 1 iteration to the thread that iteration task is completed every time, if having used size every time according to
So size iterations (axial direction part) of distribution.Judge the execution speed of per thread, the thread distribution completed to very fast iteration
Iteration more times is executed, the distribution of slower thread executes less iteration, and the iterations of per thread processing are that dynamic adjusts
, without quantitative range, it is adjusted at any time according to the disposition of thread, it is uneven to solve each cross-thread load distribution with this
The problem of weighing apparatus.
The mode of above-mentioned this distribution axial direction part is a kind of mode of dynamic dispatching, it is ensured that the load in each process
Equilibrium, to keep the processing time of each process similar, and total processing time is reduced, and ensure that the entire single core combustion of analysis
The analyzing processing speed of charge bar is greatly improved than the prior art, and load balancing refers to that approximately equivalent quantity is distributed between each thread
Work way, to make all threads all keep busy in institute's having time, make task free time minimize, to improve
Treatment effeciency.If load imbalance can cause all threads that will be synchronized at obstacle, most slow task will determine global
Time overhead.
According to the information of the analyze speed of each process remaining axial direction part of sub-distribution again, in an optional embodiment
In, first, it is determined that the speed speed of each process analysis axial direction part；Secondly, priority row is carried out to process according to speed speed
Sequence；Finally, remaining axial direction part is distributed according to priority height.
The above process is illustrated below according to an optional embodiment citing：
When analyzing single rod, since the solution procedure between axial direction part is mutually without influence, so can carry out parallel.
To being realized parallel by openMP sentences for axial direction part.Inside each single rod program, the analysis of axial direction part can be
Pass through for (i=0；i<M；I++) cycle is realized, meanwhile, multiple threads are opened by openMP sentences, axial direction part is carried out simultaneously
Row processing, for example, one shares 10 cycles, 10 cycle calculations is split and go to execute to different processes, each time cycle meter
Calculate represent calculate an axial direction part, by the analysis of entire single rod be converted into the temperature to each axial direction part, ess-strain, internal pressure,
The performances such as involucrum corrosion carry out numerical solution；Be arranged size=2, represent divided in each subtask execution recycle twice,
Two axial direction parts are namely calculated, are subtask respectively：01,23,45,67,89；10 are recycled, is divided into 3 processes
There are many division results, may be as shown in figure 5, No. 0 process executes the 0th, 1,6,7 cycle.For another example, it one 10 is shared follows
Ring is divided into 3 processes, and as size=1, subtask is respectively：0,1,2,3,4,5,6,7,8,9；10 are recycled, is divided
It, may be as shown in fig. 6, No. 1 process executes the 1st, 4 cycle to there are many division results in 3 processes.
The performance of above-mentioned axial direction part is weighed by many indexes, in an optional embodiment, axis
Can be temperature, ess-strain, internal pressure, involucrum corrosion etc. to the performance of section.
Said program is the parallel processing to each axial direction part in single rod, can also be carried out between each single rod parallel
Processing, in an optional embodiment, a kind of multiple nuclear fuel rod method for analyzing performance, including：First, multiple cores are obtained
The information of fuel rod；Secondly, the information of multiple nuclear fuel rods is distributed to multiple processes, wherein each of multiple processes into
Journey corresponds to the information of a nuclear fuel rod, and the quantity of process is identical as the quantity of nuclear fuel rod；Then, according to the letter of nuclear fuel rod
Cease the performance for analyzing multiple nuclear fuel rods simultaneously in multiple processes.
The information of above-mentioned fuel rod be can weigh the input information of some Most spent fuel rod, that is, with temperature, stress
The corresponding input informations such as strain, internal pressure, involucrum corrosion.For example, distribution of the temperature on pellet and involucrum is the core of input
The information of fuel rod, the corresponding temperature exported represent the performance of nuclear fuel rod.The input information for influencing temperature performance is also wrapped
Include the parameters such as the ring diameter of axial direction part, involucrum internal-and external diameter, gap heat transfer coefficient, pellet thermal conductivity.The corresponding fuel rod of ess-strain
Information refer to the parameters such as elasticity modulus, modulus of shearing, Poisson's ratio；The information of the corresponding fuel rod of internal pressure refers to temperature, transmitting
The parameters such as rate；The information that involucrum corrodes corresponding fuel rod refers to the parameters such as fusing point, phase transformation.
So that multiple single rods is separately sent to different calculate node (processor) through the above steps, can ask simultaneously
The related physical quantity for solving multiple fuel rods improves solution efficiency so as to shorten the solution time.Above-mentioned steps can to more sticks into
Row parallel performance is analyzed, or even carries out performance evaluation to the fuel rod of Whole core, and results of performance analysis is more compared with single rod program
Accurately.When carrying out performance evaluation to more sticks, the influence between ignoring between stick and stick carries out performance evaluation execution to each stick
It is identical operation, the difference is that the primary condition (input data) of each stick is different.It is more using the one way sequence of MPI
The parallel mode of data, as shown in fig. 7, the input data of different fuel stick is published to different processes by No. 0 process, respectively
Process carries out identical processing to input data, and different processes are to different fuel stick into trip temperature, ess-strain, internal pressure, involucrum
The performances such as corrosion carry out numerical solution.
The above method is the parallel mode between single rod and single rod, can also be in conjunction with the parallel mode in single stick, by two
Kind parallel mode is used in combination, and each single rod in the parallel mode between single rod and single rod carries out the division of axial direction part, from
And accelerate the processing speed of each single rod, the parallel method in parallel method and single rod between single rod can be more quickly and accurate
The true performance for detecting multiple fuel rods or even entire fuel assembly stick.
In an optional embodiment, fuel element performance evaluation program is developed using C Plus Plus, and design parallel
Method realizes the fuel element performance simulation of Whole core, by the Physical Process Analyses, designs parallel between stick and stick.
It gives one example below and above-mentioned concrete analysis process is described in detail：
The physical model and mathematical model (solving the mathematic(al) representation for relating to physical process) for specifying above-mentioned each module, to each
From solution equation use mathematics discrete method --- finite difference calculus carry out it is discrete, to it is discrete to matrix equation ask
Solution obtains the value of required physical quantity.First had to when discrete to fuel rod (including fuel pellet and fuel can) carry out it is axial and
Radial node division, it is axial as shown in Figure 2 to be divided into M section, radial be divided into N number of concentric ring (division methods are to wait rings herein
It is wide).Each axial direction part is solved when solution successively, to each axial direction part, it is assumed that each physical values such as temperature, work(on radial ring
Rate, stress, strain etc. are equal.It is discrete to the progress of each physical equation on the radial ring of each axial direction part, obtain matrix equation
Group obtains the value of acquired physical quantity by solution matrix equation group.
The solution procedure of single rod is described in detail by taking thermal module as an example below：
Input：Fuel can temperature outside is distributed (the outermost layer Temperature Distribution of each axial direction part)；Output：Each axial direction part
Profiling temperatures.
As shown in figure 8, passing through involucrum temperature drop equation by involucrum hull-skin temperature firstIt acquires
Involucrum internal surface temperature；Gap temperature drop equation is passed through by involucrum internal surface temperatureAcquire pellet outer surface temperature
Degree distribution；Temperature Distribution passes through to fuel radial temperature profile equation on pellet
It is carried out using finite difference calculus on the radial node of pellet discrete, while substituting into boundary conditionObtain a Matrix division：
Wherein,
Solution is programmed to it and uses chasing method, obtains fuel rod Temperature Distribution.
The embodiment of the present invention additionally provides a kind of single nuclear fuel rod performance evaluation device, which can be by obtaining mould
Block, distribution module, the first analysis module, the second analysis module realize its function.It should be noted that the one of the embodiment of the present invention
The single nuclear fuel rod performance evaluation device of kind can be used for executing a kind of single nuclear fuel rod that the embodiment of the present invention is provided
Can analysis method, a kind of single nuclear fuel rod method for analyzing performance of the embodiment of the present invention can also institute through the embodiment of the present invention
A kind of single nuclear fuel rod performance evaluation device provided executes.Fig. 9 is a kind of single core combustion according to the ... of the embodiment of the present invention
The schematic diagram of charge bar performance evaluation device.As shown in figure 9, Fig. 9 is a kind of single nuclear fuel rod according to the ... of the embodiment of the present invention
The structure chart of energy analytical equipment.A kind of single nuclear fuel rod performance evaluation device includes：Acquisition module 92, for obtaining multiple axis
To the information of section, wherein axial direction part is that single nuclear fuel rod is prolonged one section of fuel rod that axial segmentation is formed；Distribution module 94,
For the information of multiple axial direction parts to be distributed to multiple processes, wherein each process at least distributes the information of an axial direction part；The
One analysis module 96, the performance for analyzing multiple axial direction parts in the process that the information of axial direction part is distributed；Second analysis mould
Block 98, for obtaining the performance of single nuclear fuel rod according to the performance of multiple axial direction parts.
In an optional embodiment, which includes：First distribution sub module is used for multiple axial direction parts
Information distribute to multiple processes, wherein the information of the axial direction part of each course allocation predetermined number, the total quantity of axial direction part are big
In the total quantity equal to process；Second distribution sub module, for according to the analyze speed of each process remaining axis of sub-distribution again
To the information of section.
In an optional embodiment, which includes：Judging submodule, for judge each into
Journey analyzes the speed speed of axial direction part；Sorting sub-module, for carrying out priority ranking to process according to speed speed；Distribution
Module, for distributing remaining axial direction part according to priority height.
In an optional embodiment, a kind of multiple nuclear fuel rod performance analysis systems, including：Acquiring unit is used
In the information for obtaining multiple nuclear fuel rods, wherein the information of fuel rod includes temperature, ess-strain, internal pressure, involucrum corrosion；Point
Bill member, for the information of multiple nuclear fuel rods to be distributed to multiple processes, wherein each process in multiple processes corresponds to one
The information of a nuclear fuel rod, the quantity of process are identical as the quantity of nuclear fuel rod；Analytic unit, for the letter according to nuclear fuel rod
Cease the performance for analyzing multiple nuclear fuel rods simultaneously in multiple processes.
An embodiment of the present invention provides a kind of storage medium, storage medium includes the program of storage, wherein is run in program
When control storage medium where equipment execute the above method.
An embodiment of the present invention provides a kind of processor, processor includes the program of processing, wherein runs time control in program
Equipment executes the above method where processor processed.
The embodiments of the present invention are for illustration only, can not represent the quality of embodiment.
In the above embodiment of the present invention, all emphasizes particularly on different fields to the description of each embodiment, do not have in some embodiment
The part of detailed description may refer to the associated description of other embodiment.
In several embodiments provided herein, it should be understood that disclosed technology contents can pass through others
Mode is realized.Wherein, the apparatus embodiments described above are merely exemplary, for example, the unit division, Ke Yiwei
A kind of division of logic function, formula that in actual implementation, there may be another division manner, such as multiple units or component can combine or
Person is desirably integrated into another system, or some features can be ignored or not executed.Another point, shown or discussed is mutual
Between coupling, direct-coupling or communication connection can be INDIRECT COUPLING or communication link by some interfaces, unit or module
It connects, can be electrical or other forms.
The unit illustrated as separating component may or may not be physically separated, aobvious as unit
The component shown may or may not be physical unit, you can be located at a place, or may be distributed over multiple
On unit.Some or all of unit therein can be selected according to the actual needs to achieve the purpose of the solution of this embodiment.
In addition, each functional unit in each embodiment of the present invention can be integrated in a processing unit, it can also
It is that each unit physically exists alone, it can also be during two or more units be integrated in one unit.Above-mentioned integrated list
The form that hardware had both may be used in member is realized, can also be realized in the form of SFU software functional unit.
If the integrated unit is realized in the form of SFU software functional unit and sells or use as independent product
When, it can be stored in a computer read/write memory medium.Based on this understanding, technical scheme of the present invention is substantially
The all or part of the part that contributes to existing technology or the technical solution can be in the form of software products in other words
It embodies, which is stored in a storage medium, including some instructions are used so that a computer
Equipment (can be personal computer, server or network equipment etc.) execute each embodiment the method for the present invention whole or
Part steps.And storage medium above-mentioned includes：USB flash disk, read-only memory (ROM, Read-Only Memory), arbitrary access are deposited
Reservoir (RAM, Random Access Memory), mobile hard disk, magnetic disc or CD etc. are various can to store program code
Medium.
The above is only a preferred embodiment of the present invention, it is noted that for the ordinary skill people of the art
For member, various improvements and modifications may be made without departing from the principle of the present invention, these improvements and modifications are also answered
It is considered as protection scope of the present invention.
Claims (10)
1. a kind of single nuclear fuel rod method for analyzing performance, which is characterized in that including：
Obtain the information of multiple axial direction parts, wherein the axial direction part is one section that single nuclear fuel rod is prolonged to axial segmentation formation
Fuel rod；
The information of multiple axial direction parts is distributed into multiple processes, wherein each process at least distributes the letter of an axial direction part
Breath；
The performance of multiple axial direction parts is analyzed in the process that the information of the axial direction part is distributed；
The performance of the single nuclear fuel rod is obtained according to the performance of multiple axial direction parts.
2. according to the method described in claim 1, it is characterized in that, the information of multiple axial direction parts is distributed to multiple process packets
It includes：
The information of the multiple axial direction part is distributed into multiple processes, wherein the axial direction part of each course allocation predetermined number
Information, the total quantity of the axial direction part are more than or equal to the total quantity of the process；
According to the information of the analyze speed of each process remaining axial direction part of sub-distribution again.
3. according to the method described in claim 2, it is characterized in that, according to the analyze speed of each process again sub-distribution remaining
The information of axial direction part includes：
Judge the speed speed of axial direction part described in each process analysis；
Priority ranking is carried out to process according to the speed speed；
Remaining axial direction part is distributed according to priority height.
4. according to the method described in claim 1-3 any one, which is characterized in that the performance of the axial direction part includes：Temperature,
Ess-strain, internal pressure, involucrum corrosion.
5. a kind of multiple nuclear fuel rod method for analyzing performance, which is characterized in that including：
Obtain the information of multiple nuclear fuel rods；
The information of the multiple nuclear fuel rod is distributed to multiple processes, wherein each process in multiple processes corresponds to one
The information of nuclear fuel rod, the quantity of the process are identical as the quantity of the nuclear fuel rod；
Analyze the performance of multiple nuclear fuel rods simultaneously in multiple processes according to the information of the nuclear fuel rod.
6. a kind of single nuclear fuel rod performance evaluation device, which is characterized in that including：
Acquisition module, the information for obtaining multiple axial direction parts, wherein the axial direction part is that single nuclear fuel rod is prolonged axial point
Cut the one section of fuel rod to be formed；
Distribution module, for the information of multiple axial direction parts to be distributed to multiple processes, wherein each process at least distributes an institute
State the information of axial direction part；
First analysis module, the performance for analyzing multiple axial direction parts in the process that the information of the axial direction part is distributed；
Second analysis module, for obtaining the performance of the single nuclear fuel rod according to the performance of multiple axial direction parts.
7. device according to claim 6, which is characterized in that the distribution module includes：
First distribution sub module, for the information of the multiple axial direction part to be distributed to multiple processes, wherein each course allocation
The information of the axial direction part of predetermined number, the total quantity of the axial direction part are more than or equal to the total quantity of the process；
Second distribution sub module, for the information according to the analyze speed of each process remaining axial direction part of sub-distribution again.
8. a kind of multiple nuclear fuel rod performance analysis systems, which is characterized in that including：
Acquiring unit, the information for obtaining multiple nuclear fuel rods；
Dispatching Unit, for the information of the multiple nuclear fuel rod to be distributed to multiple processes, wherein each of multiple processes
Process corresponds to the information of a nuclear fuel rod, and the quantity of the process is identical as the quantity of the nuclear fuel rod；
Analytic unit, the property for analyzing multiple nuclear fuel rods simultaneously in multiple processes according to the information of the nuclear fuel rod
Energy.
9. a kind of storage medium, which is characterized in that the storage medium includes the program of storage, wherein described program right of execution
Profit requires the method described in any one of 1 to 5.
10. a kind of processor, which is characterized in that the processor is for running program, wherein right of execution when described program is run
Profit requires the method described in any one of 1 to 5.
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| TWI816560B (en) * | 2022-09-26 | 2023-09-21 | 行政院原子能委員會核能研究所 | Design method of lattice enrichment of nuclear fuel bundle of boiling water reactor |
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| CN111090943A (en) * | 2019-12-18 | 2020-05-01 | 北京科技大学 | Geometric modeling method and system for full reactor sub-channel of fast neutron reactor |
| CN111090943B (en) * | 2019-12-18 | 2021-10-12 | 北京科技大学 | Geometric modeling method and system for full reactor sub-channel of fast neutron reactor |
| CN113408147A (en) * | 2021-07-15 | 2021-09-17 | 中国科学院近代物理研究所 | Reactor fuel performance analysis and calculation method, system, storage medium and equipment |
| CN113408147B (en) * | 2021-07-15 | 2022-07-05 | 中国科学院近代物理研究所 | Reactor fuel performance analysis and calculation method, system, storage medium and equipment |
| TWI816560B (en) * | 2022-09-26 | 2023-09-21 | 行政院原子能委員會核能研究所 | Design method of lattice enrichment of nuclear fuel bundle of boiling water reactor |
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