WO2009134498A3 - A methodology for modeling the fuel rod power distribution within a nuclear reactor core - Google Patents

A methodology for modeling the fuel rod power distribution within a nuclear reactor core Download PDF

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Publication number
WO2009134498A3
WO2009134498A3 PCT/US2009/033160 US2009033160W WO2009134498A3 WO 2009134498 A3 WO2009134498 A3 WO 2009134498A3 US 2009033160 W US2009033160 W US 2009033160W WO 2009134498 A3 WO2009134498 A3 WO 2009134498A3
Authority
WO
WIPO (PCT)
Prior art keywords
fuel
fuel rod
modeling
power distribution
nuclear reactor
Prior art date
Application number
PCT/US2009/033160
Other languages
French (fr)
Other versions
WO2009134498A2 (en
Inventor
Baocheng Zhang
Original Assignee
Westinghouse Electric Company Llc
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 Westinghouse Electric Company Llc filed Critical Westinghouse Electric Company Llc
Priority to EP09739300A priority Critical patent/EP2240939A4/en
Priority to JP2010545982A priority patent/JP2011528101A/en
Priority to CN2009801048522A priority patent/CN101946253A/en
Priority to BRPI0908354A priority patent/BRPI0908354A2/en
Publication of WO2009134498A2 publication Critical patent/WO2009134498A2/en
Publication of WO2009134498A3 publication Critical patent/WO2009134498A3/en
Priority to ZA2010/05627A priority patent/ZA201005627B/en

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C5/00—Moderator or core structure; Selection of materials for use as moderator
    • 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
    • G21D3/001—Computer implemented control
    • G21D3/002—Core design; core simulations; core optimisation
    • 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)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

A method for modeling a nuclear reactor core that follows the history of each fuel pin and employs fuel pin flux form factors to explicitly track each fuel pin's fluence exposure along its axial length and uses this information to obtain fundamental data for each fuel rod, i.e. fuel rod cross-sections, for each fuel pin segment. The data obtained for the fuel pins segments are employed to adjust the fuel pin flux form factors to match the real fuel pins' history so that the fuel rod power distribution can be precisely calculated based on the fuel rod cross-sections and the flux form factors.
PCT/US2009/033160 2008-02-11 2009-02-05 A methodology for modeling the fuel rod power distribution within a nuclear reactor core WO2009134498A2 (en)

Priority Applications (5)

Application Number Priority Date Filing Date Title
EP09739300A EP2240939A4 (en) 2008-02-11 2009-02-05 A methodology for modeling the fuel rod power distribution within a nuclear reactor core
JP2010545982A JP2011528101A (en) 2008-02-11 2009-02-05 Modeling method of fuel rod power distribution in nuclear reactor
CN2009801048522A CN101946253A (en) 2008-02-11 2009-02-05 A methodology for modeling the fuel rod power distribution within a nuclear reactor core
BRPI0908354A BRPI0908354A2 (en) 2008-02-11 2009-02-05 method of modeling an axial and radial fuel rod by fuel rod power distribution of a nuclear fuel assembly
ZA2010/05627A ZA201005627B (en) 2008-02-11 2010-08-05 A methodology for modeling the fuel rod power distribution within a nuclear reactor core

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
US2900508A 2008-02-11 2008-02-11
US12/029,005 2008-02-11

Publications (2)

Publication Number Publication Date
WO2009134498A2 WO2009134498A2 (en) 2009-11-05
WO2009134498A3 true WO2009134498A3 (en) 2009-12-30

Family

ID=41255642

Family Applications (1)

Application Number Title Priority Date Filing Date
PCT/US2009/033160 WO2009134498A2 (en) 2008-02-11 2009-02-05 A methodology for modeling the fuel rod power distribution within a nuclear reactor core

Country Status (8)

Country Link
EP (1) EP2240939A4 (en)
JP (1) JP2011528101A (en)
KR (1) KR20100115754A (en)
CN (1) CN101946253A (en)
BR (1) BRPI0908354A2 (en)
TW (1) TW200949856A (en)
WO (1) WO2009134498A2 (en)
ZA (1) ZA201005627B (en)

Families Citing this family (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US8548789B2 (en) * 2008-02-11 2013-10-01 Westinghouse Electric Company Llc Methodology for modeling the fuel rod power distribution within a nuclear reactor core
FR2972839B1 (en) * 2011-03-15 2013-03-29 Areva Np METHOD FOR OPTIMIZING THE PILOTAGE OF A PRESSURIZED WATER NUCLEAR REACTOR DURING LOAD MONITORING
CN103617816B (en) * 2013-10-29 2016-06-08 中国广核集团有限公司 The measuring method of reactor core power distribution
CN105404723B (en) * 2015-10-30 2017-04-19 西安交通大学 Method for precisely calculating power distribution of fuel assembly rod
UA127699C2 (en) * 2016-09-06 2023-12-06 Вестінгхаус Електрік Свіден Аб A fuel assembly
EP3748651B1 (en) * 2018-02-01 2023-08-02 State Power Investment Corporation Research Institute Reactor three-dimensional assembly information tracking method and system
JP7438926B2 (en) 2020-12-22 2024-02-27 三菱重工業株式会社 Replacement core design method and replacement core design system
CN114840988B (en) * 2022-04-22 2024-02-23 西安交通大学 Automatic modeling method for pressurized water reactor core

Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4774050A (en) * 1986-04-10 1988-09-27 Westinghouse Electric Corp. Axial power distribution monitor and display using outputs from ex-core detectors and thermocouples
US20040022342A1 (en) * 2000-04-26 2004-02-05 Joseph Magill Method of incineration of minor actinides in nuclear reactors
US20040096101A1 (en) * 2001-08-29 2004-05-20 Masaaki Mori Calculation method of nuclear reactor core
US20050135547A1 (en) * 1998-03-11 2005-06-23 Wolfgang Schulz Control element for a nuclear reactor
US20060184286A1 (en) * 2003-06-26 2006-08-17 Framatome Anp Gmbh Method for computer modeling the core of a nuclear reactor

Family Cites Families (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
JPS55149900A (en) * 1979-05-11 1980-11-21 Hitachi Ltd Power control device for bwr type reactor
JP3023185B2 (en) * 1991-01-17 2000-03-21 株式会社東芝 Reactor core performance calculator
JP3100069B2 (en) * 1991-04-19 2000-10-16 株式会社日立製作所 Reactor operation planning method and apparatus, and reactor core characteristic monitoring apparatus
JPH11264887A (en) * 1998-03-17 1999-09-28 Toshiba Corp Reactor nuclear instrumentation system, reactor power distribution monitoring system provided with this system and reactor power monitoring method

Patent Citations (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4774050A (en) * 1986-04-10 1988-09-27 Westinghouse Electric Corp. Axial power distribution monitor and display using outputs from ex-core detectors and thermocouples
US20050135547A1 (en) * 1998-03-11 2005-06-23 Wolfgang Schulz Control element for a nuclear reactor
US20040022342A1 (en) * 2000-04-26 2004-02-05 Joseph Magill Method of incineration of minor actinides in nuclear reactors
US20040096101A1 (en) * 2001-08-29 2004-05-20 Masaaki Mori Calculation method of nuclear reactor core
US20060184286A1 (en) * 2003-06-26 2006-08-17 Framatome Anp Gmbh Method for computer modeling the core of a nuclear reactor

Non-Patent Citations (2)

* Cited by examiner, † Cited by third party
Title
IWAMOTO ET AL.: "Pin Power Reconstruction Methods of the Few-Group BWR Core Simulator NEREUS", JOURNAL OF NUCLEAR SCIENCE AND TECHNOLOGY, vol. 36, no. 12, December 1999 (1999-12-01), XP008139286, Retrieved from the Internet <URL:http://www.jstage.jst.go.jp/article/jnsU36/12/1141/_pdf> [retrieved on 20090908] *
See also references of EP2240939A4 *

Also Published As

Publication number Publication date
EP2240939A2 (en) 2010-10-20
JP2011528101A (en) 2011-11-10
WO2009134498A2 (en) 2009-11-05
BRPI0908354A2 (en) 2019-09-24
KR20100115754A (en) 2010-10-28
ZA201005627B (en) 2011-06-29
TW200949856A (en) 2009-12-01
CN101946253A (en) 2011-01-12
EP2240939A4 (en) 2012-03-21

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