CN106024080B - It is a kind of to obtain the method that reactor core netron-flux density is finely distributed - Google Patents
It is a kind of to obtain the method that reactor core netron-flux density is finely distributed Download PDFInfo
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- CN106024080B CN106024080B CN201610472997.XA CN201610472997A CN106024080B CN 106024080 B CN106024080 B CN 106024080B CN 201610472997 A CN201610472997 A CN 201610472997A CN 106024080 B CN106024080 B CN 106024080B
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- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/10—Structural combination of fuel element, control rod, reactor core, or moderator structure with sensitive instruments, e.g. for measuring radioactivity, strain
- G21C17/108—Measuring reactor flux
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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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- Engineering & Computer Science (AREA)
- Plasma & Fusion (AREA)
- General Engineering & Computer Science (AREA)
- High Energy & Nuclear Physics (AREA)
- Monitoring And Testing Of Nuclear Reactors (AREA)
Abstract
It is a kind of to obtain the method that reactor core netron-flux density is finely distributed, 1st, reactor core diffusion equation is solved using discrete variation locking nub method, obtain the netron-flux density expansion in each locking nub, 2, be finely distributed using obtaining netron-flux density expansion in step 1 and carry out the discrete reactor in-core netron-flux density that just obtains；It is discrete that the present invention uses the locking nub netron-flux density expansion of discrete variation locking nub method acquisition directly to carry out, and makes the precision that reactor in-core netron-flux density is finely distributed identical with locking nub method precision, eliminates extra error and calculation cost that reconstruct is brought.
Description
Technical field
The present invention relates to nuclear reactor design and reactor physics calculating field, and in particular to one kind obtains reactor
The method that reactor core netron-flux density is finely distributed.
Background technology
In order to ensure reactor core design safety to operation safety, it is necessary to quickly and accurately calculate reactor and related
Equipment in netron-flux density distribution situation.
The method that traditional reactor core netron-flux density widely used at present is finely distributed is " Reconstruction Method ".It is so-called
" Reconstruction Method " refers to：
1. obtain locking nub average neutron flux density using locking nub method reactor core diffusion process, face average neutron flux density,
Middle sub-information of the reactor cores such as face average neutron current density in locking nub aspect；
2. it is distributed by netron-flux density reconstructing method using known neutron information acquisition reactor core netron-flux density
Function；
3. discrete above-mentioned distribution function obtains the fine distribution of reactor core netron-flux density.
In order to ensure reconstruction accuracy, " Reconstruction Method " needs more middle sub-informations, and then has derived first with locking nub method
The middle sub-information obtained obtains netron-flux density and neutron-current of locking nub corner point etc., recycles these Given informations
(the middle sub-information and the middle sub-information of locking nub corner point that include the acquisition of locking nub method) is reconstructed.
But, on the one hand, because " Reconstruction Method " needs extra reconstruction calculations, add calculating cost and bring extra
Error；On the other hand, " Reconstruction Method " due to the middle sub-information obtained from locking nub method it is less (even if plus the letter of locking nub corner point
Breath), it is impossible to the distribution function of higher-order number is obtained, so being distributed not gentle enough region (as close to anti-in netron-flux density
Penetrate the region of layer), its reconstruction accuracy is very poor.
The content of the invention
In order to overcome the problem of above-mentioned prior art is present, reactor core is obtained it is an object of the invention to provide one kind
The method that netron-flux density is finely distributed, is finely distributed to obtain Reactor Neutron Flux Density, and the inventive method is utilized
The locking nub netron-flux density distribution expansion that discrete variation locking nub method (VNM) obtains, it can rapidly and accurately be reacted
Pile neutron flux density is finely distributed.
To achieve these goals, this invention takes following technical scheme：
It is a kind of to obtain the method that reactor core netron-flux density is finely distributed, comprise the following steps：
Step 1：Reactor core diffusion equation is solved using discrete variation locking nub method, the neutron for obtaining shape such as following formula in each locking nub leads to
Metric density expansion；
Wherein, Φ (r) is distributed for netron-flux density to be asked；fi(r) space to be made up of complete orthogonal polynomial
Basic function；For expansion coefficient；
Step 2：Just reacted using acquisition netron-flux density expansion in step 1 and so that following equation progress is discrete
Heap heap in-core netron-flux density is finely distributed
Wherein
φ (r) is to treat discrete netron-flux density；
R=(r1,r2,r3...) and it is area coordinate to be deployed；
For expansion coefficient；
V is the volume of zone of dispersion；
V is zone of dispersion to be asked.
Compared with prior art, the present invention has following outstanding feature：
It is discrete that the present invention uses the locking nub netron-flux density expansion of discrete variation locking nub method acquisition directly to carry out, and makes anti-
The precision for answering heap heap in-core netron-flux density to be finely distributed is identical with locking nub method precision, eliminates the extra error that reconstruct is brought
And calculation cost.
Brief description of the drawings
Fig. 1 is the fine distribution error figure of the two-dimentional hot group's netron-flux density of reactor core.
Embodiment
The present invention is described in further detail with reference to the accompanying drawings and detailed description：
The present invention obtains locking nub netron-flux density by discrete variation locking nub method (VNM) and is distributed expansion, is reacted
Pile neutron flux density is finely distributed.The specific calculation process of this method includes following aspect：
1. for neutron diffusion equation, netron-flux density in locking nub is deployed as follows：
The expansion coefficient for obtaining netron-flux density in locking nub in step 1 is calculated 2. being iterated using variation locking nub method
3. led to using the discrete reactor in-core neutron that just can obtain of netron-flux density expansion progress is obtained in step 1
Metric density is finely distributed.
Discrete variation locking nub method obtains netron-flux density expansion and then obtains netron-flux density in reactor core calculating
Fine distribution, creatively eliminate " Reconstruction Method " extra step, the higher neutron flux of precision can be effectively obtained
Density is finely distributed.
Result of calculation shows that the netron-flux density that the present invention results in degree of precision is finely distributed.Fig. 1 is two-dimentional pressure
The hot fine distribution error of group's netron-flux density of water-water reactor a quarter reactor core, its result calculated using fine-structure mesh locking nub is used as standard.
It can be found that the present invention has obtained the higher netron-flux density of precision and has finely been distributed.
Claims (1)
1. a kind of obtain the method that reactor core netron-flux density is finely distributed, it is characterised in that：Comprise the following steps：
Step 1：Reactor core diffusion equation is solved using discrete variation locking nub method, the neutron flux for obtaining shape such as following formula in each locking nub is close
Spend expansion；
Wherein, Φ (r) is distributed for netron-flux density to be asked；fi(r) the space base letter to be made up of complete orthogonal polynomial
Number；For expansion coefficient；
Step 2：Reactor is just obtained using acquisition netron-flux density expansion in step 1 and so that following equation progress is discrete
In-core netron-flux density is finely distributed
Wherein
φ (r) is to treat discrete netron-flux density；
R=(r1,r2,r3...) and it is area coordinate to be deployed；
For expansion coefficient；
V is the volume of zone of dispersion；
V is zone of dispersion to be asked.
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| CN201610472997.XA CN106024080B (en) | 2016-06-24 | 2016-06-24 | It is a kind of to obtain the method that reactor core netron-flux density is finely distributed |
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| CN201610472997.XA CN106024080B (en) | 2016-06-24 | 2016-06-24 | It is a kind of to obtain the method that reactor core netron-flux density is finely distributed |
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| CN106024080A CN106024080A (en) | 2016-10-12 |
| CN106024080B true CN106024080B (en) | 2017-07-28 |
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| Publication number | Priority date | Publication date | Assignee | Title |
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| CN107122331B (en) * | 2017-04-20 | 2020-03-31 | 西安交通大学 | Multi-physical coupling method in pressurized water reactor transient calculation |
| CN107145470B (en) * | 2017-04-27 | 2021-05-14 | 西安交通大学 | Expansion order self-adaption method of diffusion equation variable block method |
| CN108538416B (en) * | 2018-04-09 | 2019-08-20 | 西京学院 | A method of Nuclear Reactor Neutron Flux Density is measured based on reversible specific heat capacity method |
| CN111523233B (en) * | 2020-04-23 | 2021-12-28 | 西安交通大学 | Neutron transport calculation method for three-dimensional pressurized water reactor core |
Family Cites Families (11)
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| JP2647573B2 (en) * | 1990-06-12 | 1997-08-27 | ウエスチングハウス・エレクトリック・コーポレイション | Core power distribution monitoring device, reactor protection device, reactor core detector device, and reactor core monitoring method |
| JPH0462498A (en) * | 1990-06-29 | 1992-02-27 | Mitsubishi Atom Power Ind Inc | Measuring method for neutron flux distribution in nuclear reactor |
| JP3274904B2 (en) * | 1993-03-31 | 2002-04-15 | 株式会社東芝 | Reactor power measurement device |
| FR2796197B1 (en) * | 1999-07-05 | 2001-10-12 | Framatome Sa | METHOD AND DEVICE FOR MONITORING AT LEAST ONE OPERATING PARAMETER OF THE CORE OF A NUCLEAR REACTOR |
| CN101399091B (en) * | 2008-11-07 | 2012-02-01 | 西安交通大学 | Method for on-line monitoring neutron flux distribution of nuclear reactor core |
| US20110268239A1 (en) * | 2010-04-30 | 2011-11-03 | David Jerome Krieg | Method of calibrating excore detectors in a nuclear reactor |
| CN103020468B (en) * | 2012-12-26 | 2016-01-20 | 中山大学 | Obtain the method for nuclear reactor thermal coupling |
| CN103218512A (en) * | 2013-03-14 | 2013-07-24 | 西安交通大学 | Method for acquiring neutron angular flux density in nuclear fuel assembly |
| CN103294899A (en) * | 2013-05-10 | 2013-09-11 | 西安交通大学 | Method for calculating core neutron flux distribution of small experimental reactor |
| CN105426657B (en) * | 2015-10-30 | 2016-12-14 | 西安交通大学 | A kind of eliminate the method for control rod pointed tooth effect during reactor core calculates |
| CN105512387B (en) * | 2015-12-04 | 2018-09-28 | 中广核研究院有限公司 | A kind of fine power reconstructing method of fuel assembly |
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