MXPA06007604A - Metodo para mejorar el funcionamiento de un reactor nuclear durante la operacion de un nucleo de reactor. - Google Patents

Metodo para mejorar el funcionamiento de un reactor nuclear durante la operacion de un nucleo de reactor.

Info

Publication number
MXPA06007604A
MXPA06007604A MXPA06007604A MXPA06007604A MXPA06007604A MX PA06007604 A MXPA06007604 A MX PA06007604A MX PA06007604 A MXPA06007604 A MX PA06007604A MX PA06007604 A MXPA06007604 A MX PA06007604A MX PA06007604 A MXPA06007604 A MX PA06007604A
Authority
MX
Mexico
Prior art keywords
nuclear reactor
performance during
core operation
improving nuclear
reactor core
Prior art date
Application number
MXPA06007604A
Other languages
English (en)
Inventor
Francis Bolger
Jose Casillas
Original Assignee
Global Nuclear Fuel Americas
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 Global Nuclear Fuel Americas filed Critical Global Nuclear Fuel Americas
Publication of MXPA06007604A publication Critical patent/MXPA06007604A/es

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D3/00—Control of nuclear power plant
    • G21D3/001—Computer implemented control
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C7/00—Control of nuclear reaction
    • G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
    • G21C7/08—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of solid control elements, e.g. control rods
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21D—NUCLEAR POWER PLANT
    • G21D3/00—Control of nuclear power plant
    • G21D3/04—Safety arrangements
    • 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)
  • Chemical & Material Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Business, Economics & Management (AREA)
  • Emergency Management (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

En el metodo, el funcionamiento de un reactor nuclear puede ser mejorado al implementar una solucion operacional para el reactor nuclear utilizando por lo menos un criterio de varilla de control (S1405) con el fin de incrementar al efectividad de paralizacion rapida durante al menos una porcion de un ciclo de operacion para el reactor nuclear.
MXPA06007604A 2005-06-30 2006-06-30 Metodo para mejorar el funcionamiento de un reactor nuclear durante la operacion de un nucleo de reactor. MXPA06007604A (es)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US11/169,916 US7620139B2 (en) 2005-06-30 2005-06-30 Method of improving nuclear reactor performance during reactor core operation

Publications (1)

Publication Number Publication Date
MXPA06007604A true MXPA06007604A (es) 2007-06-08

Family

ID=37103107

Family Applications (1)

Application Number Title Priority Date Filing Date
MXPA06007604A MXPA06007604A (es) 2005-06-30 2006-06-30 Metodo para mejorar el funcionamiento de un reactor nuclear durante la operacion de un nucleo de reactor.

Country Status (7)

Country Link
US (1) US7620139B2 (es)
EP (1) EP1739684B1 (es)
JP (1) JP5379344B2 (es)
CN (1) CN1975936A (es)
ES (1) ES2371771T3 (es)
MX (1) MXPA06007604A (es)
TW (1) TWI389140B (es)

Families Citing this family (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US8433029B2 (en) * 2007-12-14 2013-04-30 Global Nuclear Fuel—Americas, LLC Determination of safety limit minimum critical power ratio
US8030957B2 (en) 2009-03-25 2011-10-04 Aehr Test Systems System for testing an integrated circuit of a device and its method of use
MX2013013269A (es) * 2011-05-13 2013-12-06 Neal Mann Metodo y aparato de control de reactor nuclear.
KR101406849B1 (ko) * 2012-12-27 2014-06-13 한국전력기술 주식회사 제어봉 삽입시간 측정을 위한 시뮬레이션 구축 방법
US10593436B2 (en) * 2013-11-21 2020-03-17 Terrapower, Llc Method and system for generating a nuclear reactor core loading distribution
CN110428919B (zh) * 2019-07-08 2023-01-17 中国核电工程有限公司 基于征兆的压水堆核电厂反应性控制策略的设计方法
CN112397211B (zh) * 2020-11-18 2022-08-30 山东核电有限公司 一种任意控制棒位置下压水堆燃料相关组件配插分析方法

Family Cites Families (17)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4330367A (en) * 1973-05-22 1982-05-18 Combustion Engineering, Inc. System and process for the control of a nuclear power system
BE838037A (fr) * 1975-02-11 1976-05-14 Commande de barre de reglage de reacteur nucleaire a la cuve sous pression
US4075057A (en) * 1975-03-21 1978-02-21 Nasa Non-equilibrium radiation nuclear reactor
JPS59211897A (ja) * 1983-05-18 1984-11-30 株式会社日立製作所 制御棒スクラム時間測定装置
JPH02257094A (ja) * 1989-09-28 1990-10-17 Toshiba Corp 原子炉停止装置
JPH03279898A (ja) * 1990-03-28 1991-12-11 Toshiba Corp 原子炉出力制御装置
JPH04265899A (ja) * 1991-02-20 1992-09-22 Hitachi Ltd 原子炉シミュレータ
JP3156976B2 (ja) * 1992-05-07 2001-04-16 株式会社東芝 制御棒駆動制御装置
JPH08166487A (ja) * 1994-12-15 1996-06-25 Toshiba Syst Technol Kk 運転計画装置
JPH09101818A (ja) * 1995-10-04 1997-04-15 Toshiba Syst Technol Kk 炉心性能監視システム
US5790616A (en) * 1996-08-09 1998-08-04 General Electric Company Method and system for determining nuclear reactor core control blade positioning
JPH10142382A (ja) * 1996-11-11 1998-05-29 Hitachi Ltd 原子炉炉心性能計算装置
US5912933A (en) * 1997-12-04 1999-06-15 General Electric Company Method and system for direct evaluation of operating limit minimum critical power ratios for boiling water reactors
US6611572B2 (en) * 2000-12-29 2003-08-26 Global Nuclear Fuel - Americas, L.L.C. Determination of operating limit minimum critical power ratio
JP2003130984A (ja) * 2001-10-29 2003-05-08 Global Nuclear Fuel-Japan Co Ltd 原子炉の炉心性能監視装置
US20040059549A1 (en) * 2002-09-19 2004-03-25 Kropaczek David Joseph Method and apparatus for evaluating a proposed solution to a constraint problem
US6862329B1 (en) * 2003-10-06 2005-03-01 Global Nuclear Fuel-Americas Llc In-cycle shuffle

Also Published As

Publication number Publication date
JP5379344B2 (ja) 2013-12-25
TWI389140B (zh) 2013-03-11
EP1739684B1 (en) 2011-10-05
TW200715304A (en) 2007-04-16
US7620139B2 (en) 2009-11-17
US20070002997A1 (en) 2007-01-04
CN1975936A (zh) 2007-06-06
ES2371771T3 (es) 2012-01-10
JP2007010661A (ja) 2007-01-18
EP1739684A1 (en) 2007-01-03

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