JP2006189439A5 - - Google Patents

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Publication number
JP2006189439A5
JP2006189439A5 JP2005371382A JP2005371382A JP2006189439A5 JP 2006189439 A5 JP2006189439 A5 JP 2006189439A5 JP 2005371382 A JP2005371382 A JP 2005371382A JP 2005371382 A JP2005371382 A JP 2005371382A JP 2006189439 A5 JP2006189439 A5 JP 2006189439A5
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JP
Japan
Prior art keywords
bundle
design
fuel
core
groups
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JP2005371382A
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English (en)
Japanese (ja)
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JP2006189439A (ja
JP5357376B2 (ja
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Priority claimed from US11/024,973 external-priority patent/US7574337B2/en
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Publication of JP2006189439A publication Critical patent/JP2006189439A/ja
Publication of JP2006189439A5 publication Critical patent/JP2006189439A5/ja
Application granted granted Critical
Publication of JP5357376B2 publication Critical patent/JP5357376B2/ja
Anticipated expiration legal-status Critical
Expired - Fee Related legal-status Critical Current

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JP2005371382A 2004-12-30 2005-12-26 原子炉の炉心用未使用燃料バンドル設計を決定する方法、及び原子炉の炉心 Expired - Fee Related JP5357376B2 (ja)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
US11/024,973 US7574337B2 (en) 2004-12-30 2004-12-30 Method of determining a fresh fuel bundle design for a core of a nuclear reactor
US11/024,973 2004-12-30

Publications (3)

Publication Number Publication Date
JP2006189439A JP2006189439A (ja) 2006-07-20
JP2006189439A5 true JP2006189439A5 (enExample) 2009-02-12
JP5357376B2 JP5357376B2 (ja) 2013-12-04

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ID=36641746

Family Applications (1)

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JP2005371382A Expired - Fee Related JP5357376B2 (ja) 2004-12-30 2005-12-26 原子炉の炉心用未使用燃料バンドル設計を決定する方法、及び原子炉の炉心

Country Status (7)

Country Link
US (1) US7574337B2 (enExample)
EP (1) EP1699057B1 (enExample)
JP (1) JP5357376B2 (enExample)
KR (1) KR101211903B1 (enExample)
CN (1) CN1819064B (enExample)
MX (1) MXPA06000104A (enExample)
TW (1) TWI366199B (enExample)

Families Citing this family (50)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US9047995B2 (en) * 2002-12-18 2015-06-02 Global Nuclear Fuel—Americas, LLC Method and system for designing a nuclear reactor core for uprated power operations
US8873698B2 (en) * 2002-12-18 2014-10-28 Global Nuclear Fuel—Americas, LLC Computer-implemented method and system for designing a nuclear reactor core which satisfies licensing criteria
US7231333B2 (en) * 2003-03-31 2007-06-12 Global Nuclear Fuel - Americas, Llc Method and arrangement for developing core loading patterns in nuclear reactors
US7200541B2 (en) * 2002-12-23 2007-04-03 Global Nuclear Fuel-Americas, Llc Method and arrangement for determining nuclear reactor core designs
US7337099B2 (en) * 2002-12-23 2008-02-26 Global Nuclear Fuel - Americas, Llc Method, arrangement and computer program for generating database of fuel bundle designs for nuclear reactors
US7424412B2 (en) * 2002-12-23 2008-09-09 Global Nuclear Fuel - Americas, Llc Method of determining nuclear reactor core design with reduced control blade density
US8185836B2 (en) * 2006-02-16 2012-05-22 Global Nuclear Fuel - Americas Llc Display, visualization, and processing tool for channel distortion and cell friction mitigation
US8582713B2 (en) * 2006-10-31 2013-11-12 Global Nuclear Fuel-Americas, Llc Method for improving energy output of a nuclear reactor, method for determining natural uranium blanket layer for a fuel bundle, and a fuel bundle having a variable blanket layer
US7472045B2 (en) * 2006-12-13 2008-12-30 Global Nuclear Fuel—Americas, LLC Method for perturbating a nuclear reactor core fuel bundle design to generate a group of designs
US7685079B2 (en) * 2006-12-21 2010-03-23 Global Nuclear Fuel - Americas, Llc Methods for evaluating robustness of solutions to constraint problems
US7633531B2 (en) 2006-12-31 2009-12-15 General Electric Company Systems and methods for quantitatively assessing the quality of an image produced by an imaging system
JP4977497B2 (ja) * 2007-03-08 2012-07-18 富士通株式会社 部品の三次元モデルの選別を行うためのプログラム、方法、システム
US20080219394A1 (en) * 2007-03-08 2008-09-11 Mccord Richard D Method and system for calculating an adjusted peak nodal power in a nuclear reactor
US20110002432A1 (en) * 2009-07-01 2011-01-06 Westinghouse Electric Company Llc Incore instrument core performance verification method
US20110246153A1 (en) * 2010-04-05 2011-10-06 Benjamin James Schultz Method for pellet cladding interaction (pci) evaluation and mitigation during bundle and core design process and operation
US9378853B2 (en) 2010-10-21 2016-06-28 Bwxt Nuclear Energy, Inc. Support structure for a control rod assembly of a nuclear reactor
US9424376B2 (en) 2011-11-18 2016-08-23 Terrapower, Llc Enhanced neutronics systems
KR101266522B1 (ko) * 2012-01-09 2013-05-24 한국전력기술 주식회사 ３차원 모델에 기반하고 몬테칼로법을 이용한 원자력발전소 노외계측기 형상처리함수 결정의 오차 감소 방법
US9620250B2 (en) 2012-02-02 2017-04-11 Bwxt Nuclear Energy, Inc. Spacer grid
US9911512B2 (en) 2012-02-27 2018-03-06 Bwxt Mpower, Inc. CRDM internal electrical connector
US9805832B2 (en) 2012-02-27 2017-10-31 Bwxt Mpower, Inc. Control rod drive mechanism (CRDM) mounting system for pressurized water reactors
US9959944B2 (en) 2012-04-12 2018-05-01 Bwxt Mpower, Inc. Self-supporting radial neutron reflector
US10102933B2 (en) 2012-04-13 2018-10-16 Bwxt Mpower, Inc. Control rod assembly impact limiter
US10124472B2 (en) 2012-04-16 2018-11-13 Bwxt Mpower, Inc. Lower end fitting locknut for nuclear fuel assembly
US9881701B2 (en) 2012-04-17 2018-01-30 Bwxt Mpower, Inc. Spacer grids with springs having improved robustness
WO2013158491A1 (en) 2012-04-17 2013-10-24 Babcock & Wilcox Mpower, Inc. Suspended upper internals for compact nuclear reactor including a mid-hanger plate
CA2870846C (en) 2012-04-17 2020-04-28 Babcock & Wilcox Mpower, Inc. Riser transition element for compact nuclear reactor
CN104246903A (zh) 2012-04-17 2014-12-24 巴布科克和威尔科克斯M能量股份有限公司 小型模块化反应堆燃料组件
US9666313B2 (en) 2012-04-17 2017-05-30 Bwxt Mpower, Inc. Small modular reactor refueling sequence
US11289209B2 (en) 2012-04-17 2022-03-29 Bwxt Mpower, Inc. Lower end fitting locating pins
US9620253B2 (en) 2012-04-17 2017-04-11 Bwxt Mpower, Inc. Riser cone apparatus to provide compliance between reactor components and minimize reactor coolant bypass flow
US9887015B2 (en) 2012-04-17 2018-02-06 Bwxt Mpower, Inc. Suspended upper internals with tie rod couplings for compact nuclear reactor
US9922731B2 (en) 2012-04-17 2018-03-20 Bwxt Mpower, Inc. Resistance welding of an end cap for nuclear fuel rods
WO2013158498A1 (en) 2012-04-17 2013-10-24 Babcock & Wilcox Mpower, Inc. Suspended upper internals for compact nuclear reactor including a lower hanger plate
US9378852B2 (en) 2012-04-17 2016-06-28 Bwxt Mpower, Inc. Spacer grids for nuclear reactor
US10593436B2 (en) 2013-11-21 2020-03-17 Terrapower, Llc Method and system for generating a nuclear reactor core loading distribution
KR101653155B1 (ko) * 2015-03-06 2016-09-02 한국원자력연구원 고속로의 노물리 시험을 위한 시험 장치 및 방법
FR3059459B1 (fr) * 2016-11-25 2019-03-15 Electricite De France Optimisation de maintenance de centrale nucleaire
CN110402467B (zh) * 2017-02-27 2023-04-28 泰拉能源公司 用于为核反应堆建模的系统和方法
CN108511093B (zh) * 2018-04-16 2019-05-03 西安交通大学 一种压水堆燃料棒束高温加热夹持实验装置
CN108597625B (zh) * 2018-05-08 2019-04-09 西安交通大学 一种研究铅基反应堆棒束通道内熔融物迁徙行为的实验装置
CN108897907A (zh) * 2018-05-25 2018-11-27 哈尔滨工程大学 一种用于反应堆堆芯热工水力分布并行计算的方法
CN109359433B (zh) * 2018-12-04 2022-08-30 中国核动力研究设计院 一种堆芯换料设计的自动化方法
CN110556169B (zh) * 2019-08-23 2022-04-08 中国原子能科学研究院 全堆芯子通道热工水力模拟的求解域划分方法
US11604906B2 (en) * 2019-09-17 2023-03-14 Dassault Systemes Simulia Corp. System and method for crashworthiness analytics in design
EP3839979B1 (en) 2019-12-17 2022-08-24 Framatome Method of determination of a nuclear core loading pattern
CN111584106B (zh) * 2020-04-17 2022-04-19 岭东核电有限公司 核电站燃料机组替代方法、装置、设备和存储介质
CN114254803B (zh) * 2021-11-10 2025-09-23 中广核研究院有限公司 换料装载方案搜索优化方法
CN117059291B (zh) * 2023-07-07 2025-09-19 卧龙电气南阳防爆集团股份有限公司 堆芯模拟器
CN118841199B (zh) * 2024-06-25 2025-09-19 中核核电运行管理有限公司 一种重水堆改进型燃料过渡堆芯提前应用rop整定值的方法

Family Cites Families (13)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPH05134079A (ja) * 1991-11-13 1993-05-28 Toshiba Corp 原子炉出力分布監視装置
JPH05142370A (ja) * 1991-11-18 1993-06-08 Toshiba Corp 原子炉の燃料集合体
JPH07260985A (ja) * 1994-03-17 1995-10-13 Hitachi Ltd 原子炉炉心設計支援装置
US5923717A (en) * 1996-01-29 1999-07-13 General Electric Company Method and system for determining nuclear core loading arrangements
US5790618A (en) * 1997-07-21 1998-08-04 General Electric Company Method and system for determining the impact of a mislocated nuclear fuel bundle loading
US6748348B1 (en) * 1999-12-30 2004-06-08 General Electric Company Design method for nuclear reactor fuel management
US20030086520A1 (en) * 2001-11-07 2003-05-08 Russell William Earl System and method for continuous optimization of control-variables during operation of a nuclear reactor
US7200541B2 (en) * 2002-12-23 2007-04-03 Global Nuclear Fuel-Americas, Llc Method and arrangement for determining nuclear reactor core designs
US7231333B2 (en) * 2003-03-31 2007-06-12 Global Nuclear Fuel - Americas, Llc Method and arrangement for developing core loading patterns in nuclear reactors
US7222061B2 (en) * 2002-12-18 2007-05-22 Global Nuclear Fuel - Americas, Llc Method and arrangement for developing rod patterns in nuclear reactors
US7337099B2 (en) * 2002-12-23 2008-02-26 Global Nuclear Fuel - Americas, Llc Method, arrangement and computer program for generating database of fuel bundle designs for nuclear reactors
US20040191734A1 (en) * 2003-03-31 2004-09-30 Russell William Earl Method and arrangement for determining fresh fuel loading patterns for nuclear reactors
US7280946B2 (en) * 2003-04-30 2007-10-09 Global Nuclear Fuel-Americas, Llc Method and arrangement for determining pin enrichments in fuel bundle of nuclear reactor

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