CN107910083A - A kind of nuclear power plant's measurement of rod worth method - Google Patents

A kind of nuclear power plant's measurement of rod worth method Download PDF

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CN107910083A
CN107910083A CN201711027029.9A CN201711027029A CN107910083A CN 107910083 A CN107910083 A CN 107910083A CN 201711027029 A CN201711027029 A CN 201711027029A CN 107910083 A CN107910083 A CN 107910083A
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mrow
rod
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mfrac
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CN107910083B (en
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孟凡锋
蔡光明
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CNNC Fujian Nuclear Power Co Ltd
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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
    • G21C17/104—Measuring reactivity
    • 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

The invention belongs to nuclear power plant's reactor physics technical field, and in particular to a kind of nuclear power plant's measurement of rod worth method.This method carves rod measuring method using dynamic and control rod worth is measured, the data processing that dynamic carves rod experiment, the measurement result of final control rod worth and relative deviation≤10% of design load are completed by using range current signal among PWR nuclear power plant out-pile nuclear measurement system.This method without the measurement into row detector background, relative to conventional dynamic carve rod method save 0.5 it is small when；Relative to traditional measurement of rod worth method (adjusting boron method, rod to carve rod method) can save 12 it is small when the refueling outage time；Rod reactivity is carved without using dynamic, purchase instrument expense (1,000,000 yuan/platform) can be saved.

Description

A kind of nuclear power plant's measurement of rod worth method
Technical field
The invention belongs to nuclear power plant's reactor physics technical field, and in particular to one kind is based on heap outer core measurement system of nuclear power plant The measurement of rod worth method of range among system.
Background technology
Nuclear power plant in order to verify heap core performance and design predicted value uniformity, it is necessary to carry out zero power physics testing.And An important content is the measurement of control rod worth in zero power physics testing.
Traditional tune boron method and change the method for rod method measurement control rod worth and take longer while can produce a large amount of waste water.For Shorten the zero power physics testing time (shortening the refueling outage cycle about 15h), reduce waste water generation, domestic and international nuclear power plant adopts successively The measurement that rod is worth is controlled with dynamic quarter rod (DRWM) method.
Nuclear power plant generally carves rod reactivity meter using dynamic and carves rod experiment, out-pile Nuclear Instrument during experiment into Mobile state at present A power range in system is carved rod reactivity meter with dynamic and is connected, and can cause an out-pile Nuclear Instrument system power range not It can use, influence reactor safety.
Therefore, research and develop, design a kind of measurement of rod worth side based on range among nuclear power plant's out-pile nuclear measurement system Method, to solve the above problems.
The content of the invention
The technical problem to be solved in the present invention is to provide a kind of nuclear power plant's measurement of rod worth method, by the method not The disabled dynamic of out-pile Nuclear Instrument system power range can be caused to carve rod measuring method to measure control rod worth, to subtract Few unit operation operation risk.
In order to realize this purpose, the present invention adopts the technical scheme that：
A kind of nuclear power plant's measurement of rod worth method, applied to nuclear power plant's zero power physics testing；Rod is carved using dynamic Measuring method measures control rod worth, by using range electric current letter among PWR nuclear power plant out-pile nuclear measurement system Number the data processing that dynamic carves rod experiment is completed, it is as follows that the dynamic of this method carves rod data handling procedure：
(1) amendment of range current value among
During dynamic carves rod experiment, the current value that range collects among out-pile nuclear measurement system is I, unit A；
Revised electric current of this electric current by the static factor be：
In formula, IIRCFor revised middle range current value, unit A；
SSF is the static modification factor of the middle range position correspondence of theoretical calculation；
(2) inverse kinematics calculate reactivity
Use revised middle range current value IIRCBe calculated based on the dynamic (dynamical) reactive inverse kinematics of point heap Reactivity：
ρ=f (IIRC) (2)
In formula, ρ is the reactivity that is calculated of inverse kinematics, unit pcm；
f(IIRC) it is according to revised middle range current value I based on point-reactor kinetic equationIRCIt is inverse to carry out reactivity The formula that dynamic calculates；
Putting the dynamic (dynamical) inverse kinematics equation of heap is：
In formula, n (t) represents the neutron-flux level of t moment, n (t)=IIRC；
L represents neutron generation time；
βieffRepresent the effective delayed neutron fraction of i-th group of neutron energy groups；
λiRepresent the decay coefficient of i-th group of neutron energy groups delayed-neutron precursor；
βieff, λiDesign load is used, is known quantity；
ciRepresent i-th group of pioneer's cuclear density, be the process variable calculated, with IIRCAnd change；
Q is outside interruption source strength, is set in formula (3) and ignores this value, q=0；
Obtain reactor core reactivity and the relation of middle range current value：
(3) control rod worth finally determines
Δρ(IRC, z)=ρ(IRC、z)-ρ(IRC、225) (5)
ρ(IRC、z’)=Δ ρ(IRC, z)×DSF(z) (6)
In formula, ρ(IRC、z)It is the control rod worth being calculated when rod position is z by formula (4), unit pcm；
ρ(IRC、z’)It is control rod worth when revised rod position is z, unit pcm；
ρ(IRC、225)The reactivity that rod is calculated in PRV head package by formula (4) in order to control, pcm；
Δρ(IRC, z)For the changes of reactivity amount relative to control rod at heap top, unit pcm；
DSF (z) is control rod worth modifying factor when rod position is z, by having the function of that the core of out-pile probe response is set Software is counted to calculate and determine according to reactor core loading and control rod translational speed, position；
ρ is calculated by formula (1), (2), (4), (5), (6)(IRC、z’), determine control rod when revised rod position is z Value.
The beneficial effect of technical solution of the present invention is：
The measurement result of control rod worth and relative deviation≤10% of design load.This method need not be into row detector background Measurement, relative to conventional dynamic carve rod method save 0.5 it is small when；
Relative to traditional measurement of rod worth method (adjusting boron method, rod to carve rod method) can save 12 it is small when refueling outage Time；
Rod reactivity is carved without using dynamic, purchase instrument expense (1,000,000 yuan/platform) can be saved.
Embodiment
Technical solution of the present invention is described in detail with reference to specific embodiment.
The function of nuclear power plant's out-pile Nuclear Instrument system is the change of continuous monitoring reactor capability, power level and power distribution Change, for power supervision, power distribution supervision, rod control program, reactor protection etc..Out-pile Nuclear Instrument system includes 2 sources and measures Cheng Tongdao, 2 middle range passages, 4 power range passages, wherein each power range passage includes 6 section detectors.
Measurement of rod worth method is based on point-reactor kinetic equation.Traditional measurement of rod worth method is in reactor core Directly reactive inverse kinematics are carried out when sub- flux quickly changes and (influenced by three-dimensional effect) using point-reactor kinetic equation to calculate Result differ larger with the reactivity of reactor core reality, control rod valency can not be completed in the case where being had a great influence by three-dimensional effect The measurement of value.And dynamic carves rod by introducing the static modification factor (SSF) and the dynamic corrections factor (DSF), noted in reactor core neutron The theoretical correction of three-dimensional effect is carried out when dose rate change is very fast, so that measurement of rod worth can be carried out quickly.These are repaiied Positive divisor is calculated by nuclear design software.It is to carve rod reactivity meter by using dynamic to adopt that conventional dynamic, which carves rod method, Collect out-pile nuclear measurement system power range electric current come complete dynamic carve rod experiment data processing.
A kind of measurement of rod worth method based on range among nuclear power plant's out-pile nuclear measurement system of the present invention, is applied to Nuclear power plant's zero power physics testing；Rod measuring method is carved using dynamic to measure control rod worth, by using presurized water reactor Range current signal completes the data processing that dynamic carves rod experiment among nuclear power plant's out-pile nuclear measurement system, and the dynamic of this method is carved Rod data handling procedure is as follows：
(1) amendment of range current value among
During dynamic carves rod experiment, the current value that range collects among out-pile nuclear measurement system is I, unit A；
Revised electric current of this electric current by the static factor be：
In formula, IIRCFor revised middle range current value, unit A；
SSF is the static modification factor of the middle range position correspondence of theoretical calculation；
(2) inverse kinematics calculate reactivity
Use revised middle range current value IIRCBe calculated based on the dynamic (dynamical) reactive inverse kinematics of point heap Reactivity：
ρ=f (IIRC) (2)
In formula, ρ is the reactivity that is calculated of inverse kinematics, unit pcm；
f(IIRC) it is according to revised middle range current value I based on point-reactor kinetic equationIRCIt is inverse to carry out reactivity The formula that dynamic calculates；
Putting the dynamic (dynamical) inverse kinematics equation of heap is：
In formula, n (t) represents the neutron-flux level of t moment, n (t)=IIRC；
L represents neutron generation time；
βieffRepresent the effective delayed neutron fraction of i-th group of neutron energy groups；
λiRepresent the decay coefficient of i-th group of neutron energy groups delayed-neutron precursor；
βieff, λiDesign load is used, is known quantity；
ciRepresent i-th group of pioneer's cuclear density, be the process variable calculated, with IIRCAnd change；
Q is outside interruption source strength, is set in formula (3) and ignores this value, q=0；
Obtain reactor core reactivity and the relation of middle range current value：
(3) control rod worth finally determines
Δρ(IRC, z)=ρ(IRC、z)-ρ(IRC、225) (5)
ρ(IRC、z’)=Δ ρ(IRC, z)×DSF(z) (6)
In formula, ρ(IRC、z)It is the control rod worth being calculated when rod position is z by formula (4), unit pcm；
ρ(IRC、z’)It is control rod worth when revised rod position is z, unit pcm；
ρ(IRC、225)The reactivity that rod is calculated in PRV head package by formula (4) in order to control, pcm；
Δρ(IRC, z)For the changes of reactivity amount relative to control rod at heap top, unit pcm；
DSF (z) is control rod worth modifying factor when rod position is z, by having the function of that the core of out-pile probe response is set Software is counted to calculate and determine according to reactor core loading and control rod translational speed, position；
ρ is calculated by formula (1), (2), (4), (5), (6)(IRC、z’), determine control rod when revised rod position is z Value.
By 102 refueling outage of Fuqing nuclear power plant, 201 refueling outages dynamic carve rod test data verification, using based on The control rod worth that range measurement data measurement obtains among out-pile nuclear measurement system is satisfied by the acceptance criteria of experiment, can replace For traditional test method.

Claims (1)

  1. A kind of 1. nuclear power plant's measurement of rod worth method, applied to nuclear power plant's zero power physics testing；It is characterized in that：Using Dynamic carves rod measuring method and control rod worth is measured, by using PWR nuclear power plant out-pile nuclear measurement system intermediate quantity Journey current signal completes the data processing that dynamic carves rod experiment, and the dynamic quarter rod data handling procedure of this method is as follows：
    (1) amendment of range current value among
    During dynamic carves rod experiment, the current value that range collects among out-pile nuclear measurement system is I, unit A；
    Revised electric current of this electric current by the static factor be：
    <mrow> <msub> <mi>I</mi> <mrow> <mi>I</mi> <mi>R</mi> <mi>C</mi> </mrow> </msub> <mo>=</mo> <mfrac> <mi>I</mi> <mrow> <mi>S</mi> <mi>S</mi> <mi>F</mi> </mrow> </mfrac> <mo>-</mo> <mo>-</mo> <mo>-</mo> <mrow> <mo>(</mo> <mn>1</mn> <mo>)</mo> </mrow> </mrow>
    In formula, IIRCFor revised middle range current value, unit A；
    SSF is the static modification factor of the middle range position correspondence of theoretical calculation；
    (2) inverse kinematics calculate reactivity
    Use revised middle range current value IIRCCarry out that reaction is calculated based on the dynamic (dynamical) reactive inverse kinematics of point heap Property：
    ρ=f (IIRC) (2)
    In formula, ρ is the reactivity that is calculated of inverse kinematics, unit pcm；
    f(IIRC) it is according to revised middle range current value I based on point-reactor kinetic equationIRCCarry out reactive inverse kinematics The formula of calculating；
    Putting the dynamic (dynamical) inverse kinematics equation of heap is：
    <mrow> <mi>&amp;rho;</mi> <mo>=</mo> <mfrac> <mn>1</mn> <mi>n</mi> </mfrac> <mo>&amp;lsqb;</mo> <mfrac> <mrow> <mi>d</mi> <mi>n</mi> </mrow> <mrow> <mi>d</mi> <mi>t</mi> </mrow> </mfrac> <mo>+</mo> <munderover> <mo>&amp;Sigma;</mo> <mrow> <mi>i</mi> <mo>=</mo> <mn>1</mn> </mrow> <mn>6</mn> </munderover> <mrow> <mo>(</mo> <mfrac> <mrow> <msub> <mi>&amp;beta;</mi> <mrow> <mi>i</mi> <mi>e</mi> <mi>f</mi> <mi>f</mi> </mrow> </msub> <mi>n</mi> </mrow> <mn>1</mn> </mfrac> <mo>-</mo> <msub> <mi>&amp;lambda;</mi> <mi>i</mi> </msub> <msub> <mi>c</mi> <mi>i</mi> </msub> <mo>)</mo> </mrow> <mo>-</mo> <mi>q</mi> <mo>&amp;rsqb;</mo> <mo>-</mo> <mo>-</mo> <mo>-</mo> <mrow> <mo>(</mo> <mn>3</mn> <mo>)</mo> </mrow> </mrow>
    In formula, n (t) represents the neutron-flux level of t moment, n (t)=IIRC；
    L represents neutron generation time；
    βieffRepresent the effective delayed neutron fraction of i-th group of neutron energy groups；
    λiRepresent the decay coefficient of i-th group of neutron energy groups delayed-neutron precursor；
    βieff, λiDesign load is used, is known quantity；
    ciRepresent i-th group of pioneer's cuclear density, be the process variable calculated, with IIRCAnd change；
    Q is outside interruption source strength, is set in formula (3) and ignores this value, q=0；
    Obtain reactor core reactivity and the relation of middle range current value：
    <mrow> <mi>&amp;rho;</mi> <mo>=</mo> <mfrac> <mn>1</mn> <msub> <mi>I</mi> <mrow> <mi>I</mi> <mi>R</mi> <mi>C</mi> </mrow> </msub> </mfrac> <mo>&amp;lsqb;</mo> <mfrac> <mrow> <msub> <mi>dI</mi> <mrow> <mi>I</mi> <mi>R</mi> <mi>C</mi> </mrow> </msub> </mrow> <mrow> <mi>d</mi> <mi>t</mi> </mrow> </mfrac> <mo>+</mo> <munderover> <mo>&amp;Sigma;</mo> <mrow> <mi>i</mi> <mo>=</mo> <mn>1</mn> </mrow> <mn>6</mn> </munderover> <mrow> <mo>(</mo> <mfrac> <mrow> <msub> <mi>&amp;beta;</mi> <mrow> <mi>i</mi> <mi>e</mi> <mi>f</mi> <mi>f</mi> </mrow> </msub> <msub> <mi>I</mi> <mrow> <mi>I</mi> <mi>R</mi> <mi>C</mi> </mrow> </msub> </mrow> <mn>1</mn> </mfrac> <mo>-</mo> <msub> <mi>&amp;lambda;</mi> <mi>i</mi> </msub> <msub> <mi>c</mi> <mi>i</mi> </msub> <mo>)</mo> </mrow> <mo>-</mo> <mi>q</mi> <mo>&amp;rsqb;</mo> <mo>-</mo> <mo>-</mo> <mo>-</mo> <mrow> <mo>(</mo> <mn>4</mn> <mo>)</mo> </mrow> </mrow>
    (3) control rod worth finally determines
    Δρ(IRC, z)=ρ(IRC、z)-ρ(IRC、225) (5)
    ρ(IRC、z’)=Δ ρ(IRC, z)×DSF(z) (6)
    In formula, ρ(IRC、z)It is the control rod worth being calculated when rod position is z by formula (4), unit pcm；
    ρ(IRC、z’)It is control rod worth when revised rod position is z, unit pcm；
    ρ(IRC、225)The reactivity that rod is calculated in PRV head package by formula (4) in order to control, pcm；
    Δρ(IRC, z)For the changes of reactivity amount relative to control rod at heap top, unit pcm；
    DSF (z) is control rod worth modifying factor when rod position is z, by having the function of that the nuclear design of out-pile probe response is soft Part is loaded according to reactor core and control rod translational speed, position calculate and determine；
    ρ is calculated by formula (1), (2), (4), (5), (6)(IRC、z’), determine control rod valency when revised rod position is z Value.
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CN109033904A (en) * 2018-07-11 2018-12-18 岭澳核电有限公司 The calibration of intermediate range protection definite value and verification method, system and terminal device
CN109192338A (en) * 2018-07-11 2019-01-11 岭澳核电有限公司 A kind of scaling method of nuclear power unit start-up course centre range protection definite value
CN109215822A (en) * 2018-09-13 2019-01-15 中国核动力研究设计院 A kind of scram reactivity measuring method
CN113241204A (en) * 2021-05-19 2021-08-10 核星核电科技(海盐)有限公司 Special system for testing reactor reactivity instrument
WO2023184956A1 (en) * 2022-04-02 2023-10-05 中广核工程有限公司 Power distribution measurement method, apparatus and system for nuclear power plant
CN117198573A (en) * 2023-11-07 2023-12-08 福建福清核电有限公司 Method for correcting core subcritical degree, method and device for cutting rod in core subcritical degree

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CN109033904A (en) * 2018-07-11 2018-12-18 岭澳核电有限公司 The calibration of intermediate range protection definite value and verification method, system and terminal device
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CN113241204A (en) * 2021-05-19 2021-08-10 核星核电科技(海盐)有限公司 Special system for testing reactor reactivity instrument
WO2023184956A1 (en) * 2022-04-02 2023-10-05 中广核工程有限公司 Power distribution measurement method, apparatus and system for nuclear power plant
CN117198573A (en) * 2023-11-07 2023-12-08 福建福清核电有限公司 Method for correcting core subcritical degree, method and device for cutting rod in core subcritical degree
CN117198573B (en) * 2023-11-07 2024-03-01 福建福清核电有限公司 Method for correcting core subcritical degree, method and device for cutting rod in core subcritical degree

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