CN109192341A - Based on the dynamic (dynamical) big reactivity measuring method of three-dimensional space-time - Google Patents
Based on the dynamic (dynamical) big reactivity measuring method of three-dimensional space-time Download PDFInfo
- Publication number
- CN109192341A CN109192341A CN201811069149.XA CN201811069149A CN109192341A CN 109192341 A CN109192341 A CN 109192341A CN 201811069149 A CN201811069149 A CN 201811069149A CN 109192341 A CN109192341 A CN 109192341A
- Authority
- CN
- China
- Prior art keywords
- neutron
- dimensional space
- measurement
- neutron flux
- time
- Prior art date
- Legal status (The legal status is an assumption and is not a legal conclusion. Google has not performed a legal analysis and makes no representation as to the accuracy of the status listed.)
- Granted
Links
Classifications
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/001—Mechanical simulators
-
- 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
Landscapes
- Physics & Mathematics (AREA)
- 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
The invention discloses the dynamic (dynamical) big reactivity measuring method of three-dimensional space-time is based on, the present invention is based on three-dimensional space-time dynamics or the modification factorsTo obtain the reactive calculation formula of stick
Description
Technical field
The present invention relates to big reactivity measurement technical fields, and in particular to is surveyed based on the dynamic (dynamical) big reactivity of three-dimensional space-time
Amount method.
Background technique
The big reactivity measurement of nuclear reactor is mainly for the control rod integral worth during physical test, card rod
The measurement process such as subcriticality, shutdown depth.
The common reactivity measuring method of nuclear power station has: adjusting boron method, changes stick method and dynamic quarter stick method.Wherein, boron method is adjusted
The micro-, integral worth by tune boron measurement of concetration control rod, but time of measuring is long and at high cost；Stick method is changed not need to adjust boron, time-consuming
It is slightly shorter, control rod integral worth can be surveyed；Dynamic carves stick method by underthrust control rod, can be in conjunction with calculating analysis and measured data
Control rod integral worth is relatively accurately measured in short period, is the widely used method of present nuclear power station.But the above method one
As for the reactivity measurement within about 2000pcm, there is limitation for big reactivity measurement.
Now common big reactivity measuring method is rod drop method, and the basic principle of rod drop method is: instantaneously falling into control rod
It in reactor in critical state, while measuring neutron count rate and changing with time, in conjunction with the neutron counting before and after scram
Rate calculates reactivity to be measured.This method passes through scram, it can be achieved that control rod integral worth, card rod subcriticality, shutdown depth
The big reactive rapid survey such as degree, but this method is based on point reactor model, shadow of the measurement result vulnerable to neutron flux three-dimensional effect
It rings, there are errors during big reactivity measurement.
Summary of the invention
It is of the invention, and it is an object of the present invention to provide the dynamic (dynamical) big reactivity measuring method of three-dimensional space-time is based on, to existing scram
Method is modified, and solves the problems, such as that there are errors using the big reactivity measurement of rod drop method progress.
The present invention is achieved through the following technical solutions:
Based on the dynamic (dynamical) big reactivity measuring method of three-dimensional space-time, comprising the following steps:
1) measurement amendment physical parameter, is obtained based on three-dimensional space-time dynamics:
A) it is based on three-dimensional space-time dynamic analysis, at the detector at each moment in calculating acquisition scram measurement process
Sub- flux absolute value φD(t), and show that scram terminates the neutron effective multiplication factor k under state stable statec；
B), by Neutron flux distribution absolute value φ (r, E, t) in the heap that obtains of three-dimensional space-time dynamics calculation analysis with
And dynamic measures the adjoint flux distribution phi of preceding critical stable state*(r, E) obtains reactor core Neutron flux distribution shape letter by following formula
Number:
In formula, r is three-dimensional space position, and E is neutron energy, and V is a certain spatial volume, and v (E) indicates that neutron energy is E
Neutron speed, φ (r, E, t) be heap in Neutron flux distribution absolute value, φ*(r, E) is that dynamic measures being total to for preceding critical stable state
Yoke Flux Distribution；
C), in being obtained by reactor core Neutron flux distribution shape function ψ (r, E, t) and neutron flux absolute value φ (r, E, t)
Sub- Flux Distribution amplitude function p (t):
D), by detector neutron flux absolute value φc(t) it is obtained at detector with neutron flux amplitude function p (t)
Sub- Flux Distribution shape ψD(t):
2) reactive modifying factor C, is obtained based on measurement amendment physical parameter:
By Neutron flux distribution amplitude function p (t) and kcFollowing formula is substituted into, obtains reactive modifying factor C:
In formula, Λ neutron generation time；β is effective delayed neutron fraction；βiFor i-th group of delayed neutron fraction；λiIt is i-th group
Delayed-neutron damping constant, above-mentioned parameter are calculated by physical computing software or other calculation methods；
3), the big reaction of measurement:
Control rod is promoted according to control rod withdrawal sequence, reactor is made to reach critical, reactor capability is adjusted, is stablized a certain
Level stablizes 3min, control rod to be measured is fallen into reactor core so that the levels of current of out-pile neutron detector meets measurement request,
Neutron current signal I is acquired simultaneouslym(t) and the stick position signal of control rod is fallen,
By detector Neutron flux distribution shape ψD(t), by following formula to measurement current signal Im(t) it carries out just
Step amendment:
Revised big reactivity ρ is obtained by following formula:
In formula, Λ neutron generation time；β is effective delayed neutron fraction；βiFor i-th group of delayed neutron fraction；λiIt is i-th group
Delayed-neutron damping constant, above-mentioned parameter are calculated by physical computing software or other calculation methods.I (t) is after optimizing
Current signal is measured, C is modifying factor.
The present invention is directed to deficiency of the big reactivity measuring method of existing reactor based on point reactor model, dynamic by three-dimensional space-time
Mechanical analysis is modified measurement process, and the big reactive three-dimensional effect mistake of point reactor model measurement can be eliminated by establishing one kind
The big reactivity measuring method of reactor of difference.This method uses the physical parameter calculated based on three-dimensional physical model, is corrected
The factor improves the deficiency of original measurement method, improves the accuracy of big reactivity measurement result.
Further, it is carried out based on three-dimensional space-time dynamics using by the Monte Carlo method of high-fidelity model analysis software
Point counting analysis, immediately arrives at the neutron flux absolute value φ at detectorD(t)；Or use the Meng Teka based on high-fidelity model
Luo Fangfa analyzes software and calculates the receptance function R that each position neutron flux of reactor core contributes neutron flux at ex-core detector
(r, E), Neutron flux distribution φ (r, E, t) in the heap obtained in conjunction with three-dimensional space-time dynamic analysis program are calculated at detector
Neutron flux absolute value φD(t), calculation formula is as follows:
In formula, r is three-dimensional space position, and E is neutron energy, and V is a certain spatial volume, and φ (r, E, t) is neutron in heap
Flux Distribution absolute value.
Compared with prior art, the present invention having the following advantages and benefits:
The present invention is directed to deficiency of the big reactivity measuring method of existing reactor based on point reactor model, dynamic by three-dimensional space-time
Mechanical analysis is modified measurement process, and the big reactive three-dimensional effect mistake of point reactor model measurement can be eliminated by establishing one kind
The big reactivity measuring method of reactor of difference.This method uses the physical parameter calculated based on three-dimensional physical model, is corrected
The factor improves the deficiency of original measurement method, improves the accuracy of big reactivity measurement result.
Specific embodiment
To make the objectives, technical solutions, and advantages of the present invention clearer, below with reference to embodiment, the present invention is made
Further to be described in detail, exemplary embodiment of the invention and its explanation for explaining only the invention, are not intended as to this
The restriction of invention.
Embodiment:
Based on the dynamic (dynamical) big reactivity measuring method of three-dimensional space-time, comprising the following steps:
1. being based on the dynamic (dynamical) big reactivity measuring method of three-dimensional space-time, which comprises the following steps:
1) measurement amendment physical parameter, is obtained based on three-dimensional space-time dynamics:
A) it is based on three-dimensional space-time dynamic analysis, at the detector at each moment in calculating acquisition scram measurement process
Sub- flux absolute value φD(t), and show that scram terminates the neutron effective multiplication factor k under state stable statec；
B), by Neutron flux distribution absolute value φ (r, E, t) in the heap that obtains of three-dimensional space-time dynamics calculation analysis with
And dynamic measures the adjoint flux distribution phi of preceding critical stable state*(r, E) obtains reactor core Neutron flux distribution shape letter by following formula
Number:
In formula, r is three-dimensional space position, and E is neutron energy, and V is a certain spatial volume, and v (E) indicates that neutron energy is E
Neutron speed, φ (r, E, t) be heap in Neutron flux distribution absolute value, φ*(r, E) is that dynamic measures being total to for preceding critical stable state
Yoke Flux Distribution
The analysis of three-dimensional space-time dynamics calculation is carried out using the Monte Carlo method analysis software based on high-fidelity model, directly
Meet the neutron flux absolute value φ obtained at detectorD(t)；Or using the Monte Carlo method analysis based on high-fidelity model
Software calculates the receptance function R (r, E) that each position neutron flux of reactor core contributes neutron flux at ex-core detector, by following formula
Neutron flux distribution φ (r, E, t) in the heap obtained in conjunction with three-dimensional space-time dynamic analysis program calculates the neutron at detector
Flux absolute value φD(t)；
In formula, r is three-dimensional space position, and E is neutron energy, and V is a certain spatial volume, and φ (r, E, t) is neutron in heap
Flux Distribution absolute value；
C), in being obtained by reactor core Neutron flux distribution shape function ψ (r, E, t) and neutron flux absolute value φ (r, E, t)
Sub- Flux Distribution amplitude function p (t):
D), by detector neutron flux absolute value φc(t) it is obtained at detector with neutron flux amplitude function p (t)
Sub- Flux Distribution shape ψD(t):
2) reactive modifying factor C, is obtained based on measurement amendment physical parameter:
In formula, Λ neutron generation time；β is effective delayed neutron fraction；βiFor i-th group of delayed neutron fraction；λiIt is i-th group
Delayed-neutron damping constant, above-mentioned parameter are calculated by physical computing software or other calculation methods；
3), the big reaction of measurement:
Control rod is promoted according to control rod withdrawal sequence, reactor is made to reach critical, reactor capability is adjusted, is stablized a certain
Level stablizes 3min, control rod to be measured is fallen into reactor core so that the levels of current of out-pile neutron detector meets measurement request,
Neutron current signal I is acquired simultaneouslym(t) and the stick position signal of control rod is fallen,
By detector Neutron flux distribution shape ψD(t), by following formula to measurement current signal Im(t) it carries out just
Step amendment:
Revised big reactivity ρ is obtained by following formula:
In formula, Λ neutron generation time；β is effective delayed neutron fraction；βiFor i-th group of delayed neutron fraction；λiIt is i-th group
Delayed-neutron damping constant, above-mentioned parameter are calculated by physical computing software or other calculation methods；I (t) is after optimizing
Current signal is measured, C is modifying factor.
Above-described specific embodiment has carried out further the purpose of the present invention, technical scheme and beneficial effects
It is described in detail, it should be understood that being not intended to limit the present invention the foregoing is merely a specific embodiment of the invention
Protection scope, all within the spirits and principles of the present invention, any modification, equivalent substitution, improvement and etc. done should all include
Within protection scope of the present invention.
Claims (2)
1. being based on the dynamic (dynamical) big reactivity measuring method of three-dimensional space-time, which comprises the following steps:
1) measurement amendment physical parameter, is obtained based on three-dimensional space-time dynamics:
A) it is based on three-dimensional space-time dynamic analysis, neutron is logical at the detector at each moment in acquisition scram measurement process by calculating
Measure absolute value φD(t), and show that scram terminates the neutron effective multiplication factor k under state stable statec；
B), Neutron flux distribution absolute value φ (r, E, t) in the heap obtained is analyzed by three-dimensional space-time dynamics calculation and moved
The adjoint flux distribution phi of critical stable state before state measures*(r, E) obtains reactor core Neutron flux distribution shape function by following formula:
In formula, r is three-dimensional space position, and E is neutron energy, and V is a certain spatial volume, and v (E) indicates that neutron energy is in E
Sub- speed, φ (r, E, t) are Neutron flux distribution absolute value in heap, φ*(r, E) is that the conjugation of critical stable state before dynamic measures is logical
Amount distribution；
C), show that neutron is logical by reactor core Neutron flux distribution shape function ψ (r, E, t) and neutron flux absolute value φ (r, E, t)
It measures distribution range function p (t):
D), by detector neutron flux absolute value φc(t) and neutron flux amplitude function p (t) show that neutron is logical at detector
Measure distribution shape part ψD(t):
2) reactive modifying factor C, is obtained based on measurement amendment physical parameter:
By Neutron flux distribution amplitude function p (t) and kcFollowing formula is substituted into, obtains reactive modifying factor C:
In formula, Λ neutron generation time；β is effective delayed neutron fraction；βiFor i-th group of delayed neutron fraction；λiIt is deferred for i-th group
Neutron attenuation constant；
3), the big reaction of measurement:
Control rod is promoted according to control rod withdrawal sequence, reactor is made to reach critical, reactor capability is adjusted, is stablized in a certain water
It is flat, so that the levels of current of out-pile neutron detector meets measurement request, stablizes 3min, control rod to be measured is fallen into reactor core, together
When acquire neutron current signal Im(t) and the stick position signal of control rod is fallen,
By detector Neutron flux distribution shape ψD(t), by following formula to measurement current signal Im(t) it is tentatively repaired
Just:
Revised big reactivity ρ is obtained by following formula:
In formula, Λ neutron generation time；β is effective delayed neutron fraction；βiFor i-th group of delayed neutron fraction；λiIt is deferred for i-th group
Neutron attenuation constant, I (t) are the measurement current signal after optimization, and C is modifying factor.
2. according to claim 1 be based on the dynamic (dynamical) big reactivity measuring method of three-dimensional space-time, which is characterized in that use
Monte Carlo method analysis software based on high-fidelity model carries out the analysis of three-dimensional space-time dynamics calculation, immediately arrives at detector
The neutron flux absolute value φ at placeD(t)；Or reactor core is calculated using the Monte Carlo method analysis software based on high-fidelity model
The receptance function R (r, E) that each position neutron flux contributes neutron flux at ex-core detector, in conjunction with three-dimensional space-time dynamics
Neutron flux distribution φ (r, E, t) in the heap that analysis program obtains, calculates the neutron flux absolute value φ at detectorD(t), it counts
It is as follows to calculate formula:
In formula, r is three-dimensional space position, and E is neutron energy, and V is a certain spatial volume, and φ (r, E, t) is neutron flux in heap
It is distributed absolute value.
Priority Applications (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201811069149.XA CN109192341B (en) | 2018-09-13 | 2018-09-13 | Large reactivity measurement method based on three-dimensional space-time dynamics |
Applications Claiming Priority (1)
| Application Number | Priority Date | Filing Date | Title |
|---|---|---|---|
| CN201811069149.XA CN109192341B (en) | 2018-09-13 | 2018-09-13 | Large reactivity measurement method based on three-dimensional space-time dynamics |
Publications (2)
| Publication Number | Publication Date |
|---|---|
| CN109192341A true CN109192341A (en) | 2019-01-11 |
| CN109192341B CN109192341B (en) | 2020-01-14 |
Family
ID=64910972
Family Applications (1)
| Application Number | Title | Priority Date | Filing Date |
|---|---|---|---|
| CN201811069149.XA Active CN109192341B (en) | 2018-09-13 | 2018-09-13 | Large reactivity measurement method based on three-dimensional space-time dynamics |
Country Status (1)
| Country | Link |
|---|---|
| CN (1) | CN109192341B (en) |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN112967825A (en) * | 2021-03-19 | 2021-06-15 | 中国核动力研究设计院 | Reactivity measurement method based on correction signal uncertainty analysis |
| CN113161029A (en) * | 2021-03-19 | 2021-07-23 | 中国核动力研究设计院 | Reactivity measurement method based on sampling signal frequency conversion analysis |
| CN113161028A (en) * | 2021-03-19 | 2021-07-23 | 中国核动力研究设计院 | Reactivity measurement method based on correction signal optimization processing |
Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP3023185B2 (en) * | 1991-01-17 | 2000-03-21 | 株式会社東芝 | Reactor core performance calculator |
| JP2006118918A (en) * | 2004-10-20 | 2006-05-11 | Toshiba Corp | Reactivity evaluation method |
| US20080192879A1 (en) * | 2007-02-08 | 2008-08-14 | Yoshihiko Ishii | Reactor start-up monitoring system |
| CN102714063A (en) * | 2009-11-06 | 2012-10-03 | 希尔莱特有限责任公司 | Systems and methods for controlling reactivity in a nuclear fission reactor |
| CN105653869A (en) * | 2016-01-05 | 2016-06-08 | 中国核动力研究设计院 | Three-dimensional transient performance analysis method for supercritical water reactor core |
-
2018
- 2018-09-13 CN CN201811069149.XA patent/CN109192341B/en active Active
Patent Citations (5)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| JP3023185B2 (en) * | 1991-01-17 | 2000-03-21 | 株式会社東芝 | Reactor core performance calculator |
| JP2006118918A (en) * | 2004-10-20 | 2006-05-11 | Toshiba Corp | Reactivity evaluation method |
| US20080192879A1 (en) * | 2007-02-08 | 2008-08-14 | Yoshihiko Ishii | Reactor start-up monitoring system |
| CN102714063A (en) * | 2009-11-06 | 2012-10-03 | 希尔莱特有限责任公司 | Systems and methods for controlling reactivity in a nuclear fission reactor |
| CN105653869A (en) * | 2016-01-05 | 2016-06-08 | 中国核动力研究设计院 | Three-dimensional transient performance analysis method for supercritical water reactor core |
Cited By (3)
| Publication number | Priority date | Publication date | Assignee | Title |
|---|---|---|---|---|
| CN112967825A (en) * | 2021-03-19 | 2021-06-15 | 中国核动力研究设计院 | Reactivity measurement method based on correction signal uncertainty analysis |
| CN113161029A (en) * | 2021-03-19 | 2021-07-23 | 中国核动力研究设计院 | Reactivity measurement method based on sampling signal frequency conversion analysis |
| CN113161028A (en) * | 2021-03-19 | 2021-07-23 | 中国核动力研究设计院 | Reactivity measurement method based on correction signal optimization processing |
Also Published As
| Publication number | Publication date |
|---|---|
| CN109192341B (en) | 2020-01-14 |
Similar Documents
| Publication | Publication Date | Title |
|---|---|---|
| CN101105986B (en) | Reactor reactivity measuring method | |
| CN204613057U (en) | Ash content of coal on-line measurement system | |
| CN109192341A (en) | Based on the dynamic (dynamical) big reactivity measuring method of three-dimensional space-time | |
| CN109117591A (en) | A kind of kinetic reactivity measurement method based on multi-detector measuring signal | |
| CN109215822A (en) | A kind of scram reactivity measuring method | |
| CN111554419B (en) | Nuclear reactor subcritical degree measuring method based on uncertainty analysis | |
| CN106782710B (en) | A kind of reactor surveys the data processing method of prompt neutron attenuation parameter | |
| CN107910083B (en) | A kind of nuclear power plant's measurement of rod worth method | |
| CN105788666A (en) | Nuclear reactor critical process control method | |
| CN104916337B (en) | A kind of data processing method of control rod calculus value measurement experiment | |
| CN109273119A (en) | Optimize the method for neutron detector position when measuring big reactivity on critical assembly | |
| CN103306663B (en) | Uranium ore logging method | |
| CN101252026B (en) | Reactor neutron source and gamma noise measuring method | |
| CN104898155A (en) | Method for measuring undercritical degree of undercritical system based on average neutron energy | |
| Meyer et al. | Total Reaction Cross Sections of Several Nuclei for 61-Mev Protons | |
| CN112967825B (en) | Reactivity measurement method based on correction signal uncertainty analysis | |
| CN107688112A (en) | A kind of method that quick measurement presurized water reactor dynamic carves rod correcting current | |
| CN105136071A (en) | Method for correcting effective area method data measurement | |
| CN111337991A (en) | Uranium ore epithermal neutron correction algorithm based on double neutron detectors | |
| CN113192659B (en) | Nuclear reactor reactivity measurement method based on primary neutron signal average sampling | |
| McClellan et al. | Photoproduction of ϕ 0 Mesons from Hydrogen and Carbon by Linearly Polarized Photons | |
| Garyaka et al. | Investigation of the main characteristics of the superhigh energy primary cosmic radiation in the gamma experiment (Mt. Aragats, Armenia) | |
| CN109324070A (en) | A kind of passive neutron assay method of uranium plutonium content in cladding waste | |
| Nakagawa et al. | Analysis of neutronics parameters measured in Phase-II experiments of the JAERI/US collaborative program on fusion blanket neutronics. Part I: Source characteristics and reaction rate distributions | |
| RU2243603C2 (en) | Method for measuring efficiency of reactor plant control rods |
Legal Events
| Date | Code | Title | Description |
|---|---|---|---|
| PB01 | Publication | ||
| PB01 | Publication | ||
| SE01 | Entry into force of request for substantive examination | ||
| SE01 | Entry into force of request for substantive examination | ||
| GR01 | Patent grant | ||
| GR01 | Patent grant |