[go: up one dir, main page]

MXPA03011912A - Metodo y sistema para realizar un analisis de seguridad de un reactor nuclear de agua hirviendo. - Google Patents

Metodo y sistema para realizar un analisis de seguridad de un reactor nuclear de agua hirviendo.

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
English (en)
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/es

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21DNUCLEAR POWER PLANT
    • G21D3/00Control of nuclear power plant
    • G21D3/001Computer implemented control
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin

Landscapes

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

Abstract

Se proporciona un metodo (60) para realizar un analisis de seguridad computarizado de un reactor nuclear de agua hirviendo (10) para facilitar que un usuario obtenga una enmienda de licencia de un cuerpo regulador nuclear para operar el reactor nuclear de agua hirviendo a una produccion termica central aumentada. El metodo tiene un numero minimo de calculos de computadora y se demuestra a traves de simulacion por computadora que la operacion segura del reactor nuclear no se arriesga. El metodo incluye restringir (62) la operacion del reactor nuclear a un dominio de operacion segura (40) determinado por un analisis de seguridad previo; y demostrar (64) que el dominio de operacion segura determinado por el analisis de seguridad previo se aplica a la operacion del reactor nuclear a la produccion termica central aumentada.
MXPA03011912A 2001-07-05 2001-07-05 Metodo y sistema para realizar un analisis de seguridad de un reactor nuclear de agua hirviendo. MXPA03011912A (es)

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 (es) 2004-03-26

Family

ID=21742687

Family Applications (1)

Application Number Title Priority Date Filing Date
MXPA03011912A MXPA03011912A (es) 2001-07-05 2001-07-05 Metodo y sistema para realizar un analisis de seguridad de un reactor nuclear de agua hirviendo.

Country Status (4)

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

Families Citing this family (7)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
RU2005116169A (ru) 2005-05-20 2006-11-27 Вадим Игоревич Дунаев (RU) Способ и система анализа и оценки безопасности технологического процесса
RU2335025C1 (ru) * 2007-07-02 2008-09-27 Общество с ограниченной ответственностью "Диаконт" Способ управления опасным технологическим процессом с нестационарными объектами
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
US8700363B2 (en) 2010-09-08 2014-04-15 The Boeing Company ETOPS IFSD risk calculator
US10990714B2 (en) 2015-12-22 2021-04-27 Bwxt Mpower, Inc. Apparatus and method for safety analysis evaluation with data-driven workflow
CN114125079B (zh) * 2021-09-07 2023-09-12 北京网藤科技有限公司 一种火电安全模拟平台协议解析系统及其解析方法
CN114036604B (zh) * 2021-10-19 2024-08-13 中国核电工程有限公司 一种新堆型气液态流出物排放源项的估算方法

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
WO2003005376A1 (en) 2003-01-16
JP2004534237A (ja) 2004-11-11
EP1407458A1 (en) 2004-04-14

Similar Documents

Publication Publication Date Title
MXPA03011912A (es) Metodo y sistema para realizar un analisis de seguridad de un reactor nuclear de agua hirviendo.
WO2005050667A3 (en) System and method for estimating helium production in stainless steel core shrouds of nuclear reactors
Atluri et al. Three-dimensional linear fracture mechanics analysis by a displacement-hybrid finite-element model
MXPA03010470A (es) Metodo de salida de energia de reactores de agua en ebullicion.
Shaw et al. Validation and evaluation of the advanced aeronautical CFD system SAUNA: A method developer's view
Meslin Safety panel and new procedures evaluation by simulator tests
Bertoglio et al. A stochastic model for turbulence at small scales-Generation of a stochastic process
Zhanguo et al. A human-machine interaction design and evaluation method by combination of scenario simulation and knowledge base
Cagliostro et al. Response of simple, scale model reactor vessels to a simulated HCDA loading
Eltayeb et al. Application of RELAP5-MV for some accident scenarios analysis of AP1000
Hiroshi et al. The'IMPACT super-simulation'project for exploring NPP fundamental phenomena
Cooper et al. Pressurized water reactor system model for control system design and analysis
Zezula Calculation of a primary-to-secondary leak by means of the ATLAS simulator with interactive operator intervention
Olding et al. LOFT small breach study using RETRAN
Vélez et al. Real time simulation of the B and W integrated control system for replica training similators
Schramm et al. Test and validation of CFD codes for the simulation of accident-typical phenomena in the reactor containment
Baisong et al. Computation of SIF of corner crack in interior wall for nozzle of nuclear vessel
Boeer et al. Track 3: growth of nuclear technology and research numerical and computational aspects of the coupled three-dimensional core/plant simulations: organization for economic cooperation and development/US nuclear regulatory commission pressurized water reactor main-steam-line-break benchmark-I. 2. Sensitivity Studies for MSLB Exercises 2 and 3 with RELAP5/PANBOX
Reed Case Study on the Development of a Hydro License Compliance Monitoring System
Carcassi et al. Research on the behaviour of MARK II Pressure Suppression Containment System during LOCA, carried out at the University of Pisa
Silva Work responsability evaluation of a nuclear power plant operator during an emergency event
Lutz et al. Presentation of geometries and transient results of TRAC-calculations
Fangzhi et al. The method research of the simulator training and examination of the nuclear electricity staff
Chao Analytical solution of the generalized Helmholtz wave equation for compressible subsonic flow and calculation of the unsteady pressure distribution about oscillating spheroids
Yakush et al. Development and application of surrogate model for assessment of ex-vessel debris bed dryout probability-15157

Legal Events

Date Code Title Description
FG Grant or registration