UA99613C2 - Способ определения трехмерного распределения мощности в активной зоне ядерного реактора - Google Patents

Способ определения трехмерного распределения мощности в активной зоне ядерного реактора

Info

Publication number
UA99613C2
UA99613C2 UAA200910391A UAA200910391A UA99613C2 UA 99613 C2 UA99613 C2 UA 99613C2 UA A200910391 A UAA200910391 A UA A200910391A UA A200910391 A UAA200910391 A UA A200910391A UA 99613 C2 UA99613 C2 UA 99613C2
Authority
UA
Ukraine
Prior art keywords
power distribution
volumetric power
determining
measuring
nuclear reactor
Prior art date
Application number
UAA200910391A
Other languages
English (en)
Ukrainian (uk)
Inventor
Антуан Готье
Давид Дюрэй
Original Assignee
Арэва Нп
Priority date (The priority date 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 date listed.)
Filing date
Publication date
Application filed by Арэва Нп filed Critical Арэва Нп
Publication of UA99613C2 publication Critical patent/UA99613C2/ru

Links

Classifications

    • 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
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D3/00—Control of nuclear power plant
    • G21D3/001—Computer implemented control
    • 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
    • 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

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • General Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

Данное изобретение относится к способам (30) трехмерного распределения мощности в активной зоне ядерного реактора с помощью набора датчиков для измерения нейтронного потока, расположенных вне корпуса реактора, а также датчиков температуры хладагента на выходе из тепловыделяющих сборок. Данный способ (30) содержит этап определения первого трехмерного распределения мощности с помощью кода нейтронного вычисления (40), мгновенно решает уравнения диффузии и обновляет изотопический баланс в активной зоне во время обеднения топлива, основанный на значениях параметров нормальной эксплуатации активной зоны, а также этап определения нового трехмерного распределения мощности на основе измерений нейтронного потока с помощью датчиков, расположенных вне реактора (80), и датчиков (100) температуры.
UAA200910391A 2007-03-19 2008-03-14 Способ определения трехмерного распределения мощности в активной зоне ядерного реактора UA99613C2 (ru)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR0701965A FR2914103B1 (fr) 2007-03-19 2007-03-19 Procede de determination de la distribution de puissance volumique du coeur d'un reacteur nucleaire

Publications (1)

Publication Number Publication Date
UA99613C2 true UA99613C2 (ru) 2012-09-10

Family

ID=38645650

Family Applications (1)

Application Number Title Priority Date Filing Date
UAA200910391A UA99613C2 (ru) 2007-03-19 2008-03-14 Способ определения трехмерного распределения мощности в активной зоне ядерного реактора

Country Status (13)

Country Link
US (1) US20100119026A1 (ru)
EP (1) EP2147441B1 (ru)
JP (1) JP5519298B2 (ru)
CN (1) CN101669176B (ru)
ES (1) ES2401824T3 (ru)
FR (1) FR2914103B1 (ru)
MA (1) MA31291B1 (ru)
PL (1) PL2147441T3 (ru)
RU (1) RU2448378C2 (ru)
SI (1) SI2147441T1 (ru)
UA (1) UA99613C2 (ru)
WO (1) WO2008132365A2 (ru)
ZA (1) ZA200907294B (ru)

Families Citing this family (48)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US8548789B2 (en) * 2008-02-11 2013-10-01 Westinghouse Electric Company Llc Methodology for modeling the fuel rod power distribution within a nuclear reactor core
FR2950466B1 (fr) 2009-09-22 2012-01-13 Areva Np Procede d'aide a l'exploitation d'un reacteur nucleaire.
US9576688B2 (en) * 2009-09-23 2017-02-21 Terrapower, Llc Movement of materials in a nuclear reactor
CN102054538B (zh) * 2009-10-30 2013-07-17 中国广东核电集团有限公司 压水堆核电站百万千瓦机组完全低中子泄漏先进四分之一换料方法及其安全分析系统
US20110268239A1 (en) * 2010-04-30 2011-11-03 David Jerome Krieg Method of calibrating excore detectors in a nuclear reactor
CN102411997B (zh) * 2011-10-25 2014-04-02 清华大学 高温气冷堆功率控制方法及系统
US9251920B2 (en) * 2012-04-11 2016-02-02 Ge-Hitachi Nuclear Energy America Llc In-situ and external nuclear reactor severe accident temperature and water level probes
CN103065433B (zh) * 2012-12-26 2014-12-24 中山大学 压水反应堆堆芯dnbr监测报警装置
CN103617816B (zh) * 2013-10-29 2016-06-08 中国广核集团有限公司 反应堆堆芯功率分布的测量方法
CN103794256B (zh) * 2013-11-19 2015-12-09 国核（北京）科学技术研究院有限公司 反应堆异常监测方法及系统
US10593436B2 (en) 2013-11-21 2020-03-17 Terrapower, Llc Method and system for generating a nuclear reactor core loading distribution
CN104575641B (zh) * 2014-12-18 2017-06-06 中国核电工程有限公司 一种提高堆外核测系统轴向功率偏差测算精度的方法及装置
CN105895175B (zh) * 2015-06-15 2017-11-07 广东核电合营有限公司 一种标定核反应堆堆芯出口热电偶的方法
JP6564628B2 (ja) * 2015-06-18 2019-08-21 三菱重工業株式会社 核燃料における軸方向測定値の再構築装置及び方法
WO2017079948A1 (zh) * 2015-11-12 2017-05-18 中广核工程有限公司 一种核电站堆芯状态的监测方法、服务器及系统
CN105448361B (zh) * 2015-11-12 2017-11-21 中广核工程有限公司 一种核电站堆芯状态的监测方法、服务器及系统
KR101687169B1 (ko) * 2016-04-06 2016-12-16 한전원자력연료 주식회사 반복 교차검증을 이용한 상관식 공차한계 설정시스템 및 그 방법
CN106126925B (zh) * 2016-06-24 2019-01-29 西安交通大学 一种改进反应堆堆芯三维中子通量密度精细分布的方法
CN106128529B (zh) * 2016-06-27 2018-02-16 中广核研究院有限公司 一种堆芯三维功率分布的在线测量方法
FR3062747B1 (fr) * 2017-02-06 2019-04-19 Altran Technologies - Altran Procede pour determiner la puissance degagee par un milieu fissile
CN107423542B (zh) * 2017-04-13 2020-01-17 西安交通大学 一种适用于逐棒计算的非均匀泄漏修正方法
US10964438B2 (en) * 2017-05-31 2021-03-30 Atomic Energy Of Canada Limited / Energie Atomique Du Canada Limitee System and method for stand-off monitoring of nuclear reactors using neutron detection
FR3069094B1 (fr) * 2017-07-12 2020-07-03 Societe Technique Pour L'energie Atomique Reacteur nucleaire avec des detecteurs neutroniques in-vessel ex-core, et procede de pilotage correspondant
FR3075449B1 (fr) * 2017-12-18 2020-01-10 Areva Np Procede de determination d'au moins une valeur limite d'au moins un parametre de fonctionnement d'un reacteur nucleaire, programme d'ordinateur et systeme electronique associes
FR3077412B1 (fr) * 2018-02-01 2021-07-23 Framatome Sa Procede de regulation de parametres operatoires d'un reacteur nucleaire et reacteur nucleaire correspondant
CN108897907A (zh) * 2018-05-25 2018-11-27 哈尔滨工程大学 一种用于反应堆堆芯热工水力分布并行计算的方法
FR3085787B1 (fr) * 2018-09-12 2020-10-23 Framatome Sa Procede d'exploitation d'un reacteur nucleaire avec calcul du rftc en ligne, reacteur nucleaire correspondant
CN109767854B (zh) * 2019-01-21 2022-07-08 中国科学院合肥物质科学研究院 一种基于堆外测量数据的反应堆内中子三维分布测量系统
CN109830317B (zh) * 2019-01-29 2023-03-24 中山大学 一种基于跟踪计算的堆芯功率本征正交分解在线重构方法
CN110853782B (zh) * 2019-11-26 2021-07-16 西南科技大学 一种反应堆堆芯中子通量三维分布测量系统及其测量方法
CN111489842B (zh) * 2020-04-20 2023-04-14 上海核星核电科技有限公司 一种在氙毒尚未平衡时实施压水堆堆芯功率分布测量的方法
CN111799000B (zh) * 2020-06-02 2021-12-17 江苏核电有限公司 一种压水堆首炉堆芯无外加一次中子源的逼近临界方法
CN112069441B (zh) * 2020-07-16 2022-03-18 中山大学 一种堆芯瞬态三维功率分布在线重构方法
CN112133462B (zh) * 2020-09-24 2022-07-29 中国核动力研究设计院 一种临界装置功率刻度方法
CN112366011B (zh) * 2020-10-27 2022-03-01 中国核动力研究设计院 一种热管反应堆核功率的控制方法及系统
JP7438926B2 (ja) * 2020-12-22 2024-02-27 三菱重工業株式会社 取替炉心設計方法及び取替炉心設計システム
CN112989595B (zh) * 2021-03-09 2022-12-09 西安交通大学 一种压水堆堆芯瞬态精细功率重构方法
CN113065241B (zh) * 2021-03-22 2022-10-28 西安交通大学 一种预测超临界二氧化碳冷却堆燃料元件主要参数的方法
CN113205896B (zh) * 2021-03-26 2024-03-15 中广核研究院有限公司 核反应堆堆芯监测方法、装置、计算机设备和存储介质
CN113192660B (zh) * 2021-04-20 2024-06-07 广东核电合营有限公司 核电站堆芯测量系统参数调整方法、装置、设备及介质
CN113409975B (zh) * 2021-06-17 2022-11-15 中国核动力研究设计院 基于模型降阶和数据同化的堆芯功率分布监测方法及系统
CN113421669B (zh) * 2021-06-17 2022-04-01 中国核动力研究设计院 基于局部非线性修正的堆芯功率分布在线重构方法及系统
CN113935567B (zh) * 2021-08-27 2024-01-16 中核龙原科技有限公司 一种核电厂提前停堆换料燃料经济损失的定量评估方法
CN114171219B (zh) * 2021-12-08 2022-06-24 西安交通大学 一种化学环境下纳米流体池式沸腾实验系统和实验方法
CN114758802B (zh) * 2022-04-01 2023-05-16 华能核能技术研究院有限公司 多普勒发热点功率确定方法、装置以及存储介质
CN115408861B (zh) * 2022-08-31 2023-11-10 中国核动力研究设计院 用于反应堆运行参数优化的数据同化方法、系统及终端
CN115862912B (zh) * 2023-02-27 2023-05-02 西安交通大学 一种动态氙条件下压水堆堆芯功率分布测量方法
CN118094364A (zh) * 2024-02-27 2024-05-28 阳江核电有限公司 一种反应堆堆芯象限功率倾斜状态评价方法

Family Cites Families (13)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4711753A (en) * 1986-03-19 1987-12-08 Westinghouse Electric Corp. Calibration of a nuclear reactor core parameter predictor
US4774049A (en) * 1986-04-10 1988-09-27 Westinghouse Electric Corp. Two and three dimensional core power distribution monitor and display
US4774050A (en) * 1986-04-10 1988-09-27 Westinghouse Electric Corp. Axial power distribution monitor and display using outputs from ex-core detectors and thermocouples
US5024801A (en) * 1989-05-01 1991-06-18 Westinghouse Electric Corp. Reactor core model update system
US5108694A (en) * 1991-08-23 1992-04-28 Westinghouse Electric Corp. Power distribution measuring system employing gamma detectors outside of nuclear reactor vessel
US5225147A (en) * 1991-09-17 1993-07-06 General Physics International Engineering & Simulation, Inc. Real time analysis of light water core neutronics
JP2696049B2 (ja) * 1992-10-08 1998-01-14 株式会社東芝 原子炉炉心核特性模擬装置
JPH0772282A (ja) * 1993-07-07 1995-03-17 Toshiba Corp 原子炉の炉心性能推定方法およびその装置
FR2753299B1 (fr) * 1996-09-12 1999-03-05 Commissariat Energie Atomique Dispositif miniaturise, auto-alimente et a reponse rapide, pour la detection etagee d'un flux neutronique, notamment dans un reacteur nucleaire
US6535568B1 (en) * 1999-12-30 2003-03-18 Global Nuclear Fuel -- Americas Llc Method and system for generating thermal-mechanical limits for the operation of nuclear fuel rods
US6493412B1 (en) * 2000-10-11 2002-12-10 Westinghouse Electric Company Llc Method of calibrating exit thermocouples in a nuclear reactor
WO2002095765A2 (de) * 2001-05-18 2002-11-28 Framatome Anp Gmbh Verfahren zum zusammensetzen eines druckwasserreaktor-kernes und entsprechender druckwasserreaktorkern
DE60305182T2 (de) * 2003-10-01 2007-03-08 Framatome Anp Brennstabbündel für einen Druckwasserkernreaktor mit Brennstäben mit zwei Gadoliniumgehalten

Also Published As

Publication number Publication date
ES2401824T3 (es) 2013-04-24
CN101669176A (zh) 2010-03-10
MA31291B1 (fr) 2010-04-01
US20100119026A1 (en) 2010-05-13
JP5519298B2 (ja) 2014-06-11
FR2914103A1 (fr) 2008-09-26
FR2914103B1 (fr) 2009-12-18
EP2147441B1 (fr) 2012-12-26
CN101669176B (zh) 2014-02-19
PL2147441T3 (pl) 2013-06-28
ZA200907294B (en) 2010-12-29
JP2010522319A (ja) 2010-07-01
WO2008132365A3 (fr) 2008-12-31
SI2147441T1 (sl) 2013-05-31
EP2147441A2 (fr) 2010-01-27
RU2448378C2 (ru) 2012-04-20
WO2008132365A2 (fr) 2008-11-06
RU2009137958A (ru) 2011-04-27

Similar Documents

Publication Publication Date Title
UA99613C2 (ru) Способ определения трехмерного распределения мощности в активной зоне ядерного реактора
CN105895175B (zh) 一种标定核反应堆堆芯出口热电偶的方法
Yang An LMR core thermal-hydraulics code based on the ENERGY model
TW200949856A (en) A methodology for modeling the fuel rod power distribution within a nuclear reactor core
SE0801323L (sv) Metod och apparat för att övervaka driften av en kärnreaktor
CN104715141B (zh) 一种压水堆核电厂氚排放源项计算方法
WO2008147371A1 (en) Electrochemical corrosion potential device and method
CN105136584A (zh) 一种辐照后rpv钢0.5t-ct试样参考温度t0测试方法
KR101266522B1 (ko) ３차원 모델에 기반하고 몬테칼로법을 이용한 원자력발전소 노외계측기 형상처리함수 결정의 오차 감소 방법
Nakajima et al. A simple model of reactor cores for reactor neutrino flux calculations for the KamLAND experiment
Karlson Continuing advancements in in-core power distribution measurement methods using SIMULATE-3 AND CECOR 3.4
RU2465660C1 (ru) Способ определения парового коэффициента реактивности
Black et al. Origin and validity of graphite dosimetry units and related conversion factors
Hartwell et al. Determination of the AGR-1 capsule to FPMS spectrometer transport volumes from leadout flow test data
Toth et al. Investigation of coolant mixing in head parts of VVER-440 fuel assemblies with burnable poison
Rhodes et al. Benchmarking of CASMO-5 ENDF/B-vii nuclear data against critical experiments
Yua et al. A Study on Pin-wise Macroscopic Depletion of PWRs in the Conventional Two-step Reactor Analysis
Hudelot et al. OCEAN: an ambitious experimental program for the qualification of integral capture cross sections of neutron absorbers
Pepelyshev et al. Experimental evaluation of IBR-2M kinetics parameters from stochastic power noise
Kwon et al. Development of Fast running DNBR calculation code
Gonzalez Vargas Advanced Reactor Physics Methods for Transient Analysis of Boiling Water Reactors
Motalab et al. Investigation of the Power Coefficient of Reactivity of 3D CANDU Reactor through Detailed Monte Carlo Analysis
Datta et al. Very First Measurement of the Two-Photon Exchange Contribution to the Elastic Electron-Neutron Scattering Cross Section using BigBite and Super BigBite Spectrometers in Jefferson Lab's Hall A
Feng et al. Research Progress on Irradiation Effects of RPV Materials
Reinecke et al. ICONE15-10313 PERFORMANCE OF CATALYTIC RECOMBINERS FOR HYDROGEN MITIGATION IN SEVERE ACCIDENTS UNDER OXYGEN DEPLETION CONDITIONS