JP2004534237A5 - - Google Patents

Download PDF

Info

Publication number
JP2004534237A5
JP2004534237A5 JP2003511256A JP2003511256A JP2004534237A5 JP 2004534237 A5 JP2004534237 A5 JP 2004534237A5 JP 2003511256 A JP2003511256 A JP 2003511256A JP 2003511256 A JP2003511256 A JP 2003511256A JP 2004534237 A5 JP2004534237 A5 JP 2004534237A5
Authority
JP
Japan
Prior art keywords
core
reactor
increased
thermal power
power
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.)
Withdrawn
Application number
JP2003511256A
Other languages
English (en)
Japanese (ja)
Other versions
JP2004534237A (ja
Filing date
Publication date
Application filed filed Critical
Priority claimed from PCT/US2001/021327 external-priority patent/WO2003005376A1/en
Publication of JP2004534237A publication Critical patent/JP2004534237A/ja
Publication of JP2004534237A5 publication Critical patent/JP2004534237A5/ja
Withdrawn legal-status Critical Current

Links

JP2003511256A 2001-07-05 2001-07-05 沸騰水型原子炉の安全解析を実行する方法及びシステム Withdrawn JP2004534237A (ja)

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 (2)

Publication Number Publication Date
JP2004534237A JP2004534237A (ja) 2004-11-11
JP2004534237A5 true JP2004534237A5 (https=) 2008-09-04

Family

ID=21742687

Family Applications (1)

Application Number Title Priority Date Filing Date
JP2003511256A Withdrawn JP2004534237A (ja) 2001-07-05 2001-07-05 沸騰水型原子炉の安全解析を実行する方法及びシステム

Country Status (4)

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

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
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 (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

Similar Documents

Publication Publication Date Title
Allison et al. Role of RELAP/SCDAPSIM in nuclear safety
Kozmenkov et al. Validation and verification of the coupled neutron kinetic/thermal hydraulic system code DYN3D/ATHLET
EP2077561A1 (en) Thermal limit analysis with hot-channel model for boiling water reactors
Adorni et al. Analysis of partial and total flow blockage of a single fuel assembly of an MTR research reactor core
JP2004534237A5 (https=)
Gorman et al. TRACE system code benchmark of Station Blackout of a NuScale-like reactor and comparison with NuScale simulator
Ball Sensitivity studies of modular high-temperature gas-cooled reactor postulated accidents
Espinoza et al. Investigations of the VVER-1000 coolant transient benchmark phase 1 with the coupled system code RELAP5/PARCS
Ahmed The impact of emergency operating safety procedures on mitigation the nuclear thermal power plant severe accident
JP5052744B2 (ja) 原子炉の炉心の燃料束構成を判定する方法
Yu et al. Numerical assessment of LOCA experiments of RD-14M using MARS-KS code
Niu et al. Operation characteristics analysis of supercritical CO2 reactor based on neutronics and thermal-hydraulics coupling
Bielen et al. NRC’s methodology to estimate fuel dispersal during a large break loss of coolant accident
JP2004534237A (ja) 沸騰水型原子炉の安全解析を実行する方法及びシステム
Nasir et al. Effect of high density dispersion fuels on transient behavior of MTR type research reactor under multiple reactivity transients
Peakman et al. Core-wide multi-physics simulation of fuel behaviour during large-break LOCA using NEXUS
Lin et al. The development and assessment of TRACE/PARCS model for Lungmen ABWR
Kim et al. Development of fully coupled FRAPTRAN with MARS-KS code system for calculation of fuel behavior during LOCA
Davis Thermal-hydraulic analyses of transients in an actinide-burner reactor cooled by forced convection of lead–bismuth
Pericas et al. Relap/Scdapsim and Asyst Ver 3 Fukushima Related Activities
Planchon et al. The Experimental Breeder Reactor II Inherent Shutdown and Heat Removal Tests–Results and Analysis
D'Auria The BWR stability issue
Greenquist et al. High-Burnup BWR LOCA Burst Analysis Using High-Fidelity Multiphysics Simulations
Tsai et al. The design assessment of limiting transient event by RETRAN-02 and VIPRE-01 for Lungmen ABWR
Mascari et al. Status of the Independent Validation of TRACE Code for SMR Safety Analyses