ES2572140T3 - Sistemas de protección y procedimientos de operación para reactores nucleares de agua en ebullición - Google Patents

Sistemas de protección y procedimientos de operación para reactores nucleares de agua en ebullición

Info

Publication number
ES2572140T3
ES2572140T3 ES07123129T ES07123129T ES2572140T3 ES 2572140 T3 ES2572140 T3 ES 2572140T3 ES 07123129 T ES07123129 T ES 07123129T ES 07123129 T ES07123129 T ES 07123129T ES 2572140 T3 ES2572140 T3 ES 2572140T3
Authority
ES
Spain
Prior art keywords
reactor
power
dependent
set point
high pressure
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.)
Active
Application number
ES07123129T
Other languages
English (en)
Inventor
Randall Howard Jacobs
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
General Electric Co
Original Assignee
General Electric Co
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 General Electric Co filed Critical General Electric Co
Application granted granted Critical
Publication of ES2572140T3 publication Critical patent/ES2572140T3/es
Active legal-status Critical Current
Anticipated expiration legal-status Critical

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • 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
    • 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)
  • Business, Economics & Management (AREA)
  • Emergency Management (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Structure Of Emergency Protection For Nuclear Reactors (AREA)

Abstract

Un sistema de protección para un reactor (102) nuclear de agua en ebullición, estando configurado el sistema de protección para: medir y/o calcular la potencia (P) del reactor; supervisar la presión de funcionamiento del reactor; calcular un primer punto de consigna de alta presión del reactor dependiente de la potencia (HRPS100) que se corresponde con un 100 % de potencia del reactor; determinar al menos un segundo punto de consigna de alta presión del reactor dependiente de la potencia (PDHRPS) que se corresponde con al menos un valor porcentual de potencia del reactor en un dominio de funcionamiento del reactor (102), basándose en la potencia (P) del reactor medida y/o calculada; en el que el al menos un segundo punto de consigna de alta presión del reactor dependiente de la potencia (PDHRPS) es menor que el primer punto de consigna de alta presión del reactor dependiente de la potencia (HRPS100) que se corresponde con un 100 % de potencia del reactor; en el que el sistema de protección está configurado adicionalmente para iniciar una parada de emergencia del reactor y/o una alarma y/o una advertencia si la presión del reactor supervisada es mayor que el primer punto de consigna de alta presión del reactor dependiente de la potencia (HRPS100) o el al menos un segundo punto de consigna de alta presión del reactor dependiente de la potencia (PDHRPS); en el que el sistema de protección está configurado adicionalmente de tal modo que el al menos un segundo punto de consigna de alta presión dependiente de la potencia (PDHRPS) se calcula como una u otra de: 1) PDHRPS >= presión de funcionamiento del reactor + HRPS100-RP100 en la que RP100 representa la presión nominal del reactor que se corresponde con un 100 % de potencia; y 2) PDHRPS >= HRPS100-S * (P/P0) en la que S representa una pendiente.
ES07123129T 2006-12-21 2007-12-13 Sistemas de protección y procedimientos de operación para reactores nucleares de agua en ebullición Active ES2572140T3 (es)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US11/642,920 US7634043B2 (en) 2006-12-21 2006-12-21 Protection systems for and methods of operating nuclear boiling water reactors

Publications (1)

Publication Number Publication Date
ES2572140T3 true ES2572140T3 (es) 2016-05-30

Family

ID=39146884

Family Applications (1)

Application Number Title Priority Date Filing Date
ES07123129T Active ES2572140T3 (es) 2006-12-21 2007-12-13 Sistemas de protección y procedimientos de operación para reactores nucleares de agua en ebullición

Country Status (4)

Country Link
US (2) US7634043B2 (es)
EP (1) EP1936636B1 (es)
JP (1) JP2008157944A (es)
ES (1) ES2572140T3 (es)

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US20130266107A1 (en) 2012-03-16 2013-10-10 Westinghouse Electric Company Llc Methods for protection of nuclear reactors from thermal hydraulic/neutronic core instability
US10822112B2 (en) * 2018-02-14 2020-11-03 General Electric Company Slope-based event detection for turbine engines

Family Cites Families (14)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB1200951A (en) * 1967-03-25 1970-08-05 Gen Electric Canada Nuclear reactor shutdown system
US3979255A (en) * 1973-09-04 1976-09-07 Combustion Engineering, Inc. Method for operating a system with a variable excursion margin setpoint
JPH02240599A (ja) * 1989-03-14 1990-09-25 Hitachi Ltd 原子炉の圧力制御装置
JPH03282399A (ja) * 1990-03-30 1991-12-12 Toshiba Corp 原子力プラントの運転方法
US5309485A (en) * 1992-07-06 1994-05-03 General Electric Company Core automated monitoring system
US5268939A (en) * 1992-10-19 1993-12-07 General Electric Company Control system and method for a nuclear reactor
US5528639A (en) * 1994-08-01 1996-06-18 General Electric Company Enhanced transient overpower protection system
US5586156A (en) * 1995-07-14 1996-12-17 General Electric Company Reactor protection system with automatic self-testing and diagnostic
US5621776A (en) * 1995-07-14 1997-04-15 General Electric Company Fault-tolerant reactor protection system
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
US6198786B1 (en) * 1998-05-22 2001-03-06 General Electric Company Methods of reactor system pressure control by reactor core power modulation
US6697447B1 (en) * 1999-12-30 2004-02-24 General Electric Company Maximum extended load line limit analysis for a boiling water nuclear reactor
US6532550B1 (en) * 2000-02-10 2003-03-11 Westinghouse Electric Company Llc Process protection system
US6928132B2 (en) * 2001-12-19 2005-08-09 General Electric Company Methods and apparatus for operating a system

Also Published As

Publication number Publication date
US7912170B2 (en) 2011-03-22
US7634043B2 (en) 2009-12-15
EP1936636A3 (en) 2013-02-13
EP1936636B1 (en) 2016-03-09
EP1936636A2 (en) 2008-06-25
US20080152066A1 (en) 2008-06-26
JP2008157944A (ja) 2008-07-10
US20100091928A1 (en) 2010-04-15

Similar Documents

Publication Publication Date Title
BR0308072A (pt) sistemas de células de combustìveis e método de proteção de célula de combustìvel
US20130063269A1 (en) Real time monitoring system of spent fuel pool and method thereof
ES2572140T3 (es) Sistemas de protección y procedimientos de operación para reactores nucleares de agua en ebullición
BR112015003341B8 (pt) Sistema e método de indicação visual
EP2458178A3 (en) Turbine performance diagnositic system and methods
CN104217774A (zh) 核电站工艺辐射监测方法和系统
MY208654A (en) Corium localizing and cooling system of a nuclear reactor
ES2546928B2 (es) Sistema de inyección de hidrógeno de arranque/parada para reactores de agua en ebullición (BWRs), y procedimiento para el mismo
CN106448764A (zh) 核电站乏燃料水池监测系统、方法
ZA202300142B (en) Corium localizing and cooling system of a nuclear reactor
AR041809A1 (es) Sistema y metodo de gestion de la manta de gas
CN104373331A (zh) 一种消防泵水流检测控制装置
MX362282B (es) Sistema de ventilacion de contencion con modo pasivo para reactores de agua en ebullicion (bwr) y metodo del mismo.
EP4489176A3 (en) External sensing for monitoring health of vehicle electric energy storage
KR20070050900A (ko) 수배전반 내부 위험감시용 아크, 열, 가스 감지센서를내장한 최대수요전력 관리장치
JP2016045121A (ja) 沸騰水型原子力発電所
CN217058965U (zh) 一种静压式液位计专用保护工具
CN203313956U (zh) 一种红外技术的plc控制柜
CN220251124U (zh) 用于地埋水厂的防淹报警系统及装置
BR112022020060A2 (pt) Método de aviso de anormalidade de bateria e dispositivo de aviso de anormalidade de bateria
JP2008157944A5 (es)
ZA202300141B (en) Corium localizing and cooling system of a nuclear reactor
CN204142657U (zh) 一种射线探伤连锁装置
CN204115956U (zh) 一种带数显功能的仪器
Hotellier et al. Safety concept of a self-sustaining PEM hydrogen electrolyzer system