MXPA03011912A - Method and system for performing a safety analysis of a boiling water nuclear reactor. - Google Patents

Method and system for performing a safety analysis of a boiling water nuclear reactor.

Info

Publication number
MXPA03011912A
MXPA03011912A MXPA03011912A MXPA03011912A MXPA03011912A MX PA03011912 A MXPA03011912 A MX PA03011912A MX PA03011912 A MXPA03011912 A MX PA03011912A MX PA03011912 A MXPA03011912 A MX PA03011912A MX PA03011912 A MXPA03011912 A MX PA03011912A
Authority
MX
Mexico
Prior art keywords
nuclear reactor
safety analysis
boiling water
water nuclear
thermal output
Prior art date
Application number
MXPA03011912A
Other languages
Spanish (es)
Inventor
Marquino Wayne
Original Assignee
Gen Electric
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 Gen Electric filed Critical Gen Electric
Publication of MXPA03011912A publication Critical patent/MXPA03011912A/en

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
    • 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

Abstract

A method (60) for performing a computerized safety analysis of a boiling water nuclear reactor (10) to facilitate a user in obtaining a licence amendment from a nuclear regulatory body to operate the boiling water nuclear reactor at an increased core thermal output is provided. The method has a minimum number of computer calculations and is demonstrated through computer simulation that safe operation of the nuclear reactor is not compromised. The method includes constraining (62) operation of the nuclear reactor to a safe operating domain (40) determined by a previous safety analysis, and demonstrating (64) that the safe operating domain determined by the previous safety analysis applies to the operation of the nuclear reactor at the increased core thermal output.
MXPA03011912A 2001-07-05 2001-07-05 Method and system for performing a safety analysis of a boiling water nuclear reactor. MXPA03011912A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
PCT/US2001/021327 WO2003005376A1 (en) 2001-07-05 2001-07-05 Method and system for performing a safety analysis of a boiling water nuclear reactor

Publications (1)

Publication Number Publication Date
MXPA03011912A true MXPA03011912A (en) 2004-03-26

Family

ID=21742687

Family Applications (1)

Application Number Title Priority Date Filing Date
MXPA03011912A MXPA03011912A (en) 2001-07-05 2001-07-05 Method and system for performing a safety analysis of a boiling water nuclear reactor.

Country Status (4)

Country Link
EP (1) EP1407458A1 (en)
JP (1) JP2004534237A (en)
MX (1) MXPA03011912A (en)
WO (1) WO2003005376A1 (en)

Families Citing this family (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
RU2005116169A (en) 2005-05-20 2006-11-27 Вадим Игоревич Дунаев (RU) METHOD AND SYSTEM OF ANALYSIS AND ASSESSMENT OF SAFETY OF A TECHNOLOGICAL PROCESS
US8700363B2 (en) 2010-09-08 2014-04-15 The Boeing Company ETOPS IFSD risk calculator
US9753894B2 (en) 2010-09-08 2017-09-05 The Boeing Company Establishing availability of a two-engine aircraft for an ETOPS flight or an ETOPS flight path for a two-engine aircraft
US10990714B2 (en) 2015-12-22 2021-04-27 Bwxt Mpower, Inc. Apparatus and method for safety analysis evaluation with data-driven workflow
CN114125079B (en) * 2021-09-07 2023-09-12 北京网藤科技有限公司 Thermal power safety simulation platform protocol analysis system and analysis method thereof

Family Cites Families (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS5552998A (en) * 1978-10-16 1980-04-17 Hitachi Ltd Reactor recirculation flow rate control device
US5293411A (en) * 1989-07-14 1994-03-08 Hitachi, Ltd. Nuclear reactor power control method and device
US5524128A (en) * 1993-11-17 1996-06-04 Entergy Operations, Inc. Boiling water reactor stability control
US5528639A (en) * 1994-08-01 1996-06-18 General Electric Company Enhanced transient overpower protection system
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

Also Published As

Publication number Publication date
EP1407458A1 (en) 2004-04-14
WO2003005376A1 (en) 2003-01-16
JP2004534237A (en) 2004-11-11

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