BRPI0908354A2 - method of modeling an axial and radial fuel rod by fuel rod power distribution of a nuclear fuel assembly - Google Patents

method of modeling an axial and radial fuel rod by fuel rod power distribution of a nuclear fuel assembly

Info

Publication number
BRPI0908354A2
BRPI0908354A2 BRPI0908354A BRPI0908354A BRPI0908354A2 BR PI0908354 A2 BRPI0908354 A2 BR PI0908354A2 BR PI0908354 A BRPI0908354 A BR PI0908354A BR PI0908354 A BRPI0908354 A BR PI0908354A BR PI0908354 A2 BRPI0908354 A2 BR PI0908354A2
Authority
BR
Brazil
Prior art keywords
fuel rod
modeling
axial
power distribution
radial
Prior art date
Application number
BRPI0908354A
Other languages
Portuguese (pt)
Inventor
Zhang Baocheng
Original Assignee
Westinghouse Electric Co 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 Co Llc filed Critical Westinghouse Electric Co Llc
Publication of BRPI0908354A2 publication Critical patent/BRPI0908354A2/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)
BRPI0908354A 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 BRPI0908354A2 (en)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
US2900508A 2008-02-11 2008-02-11
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

Publications (1)

Publication Number Publication Date
BRPI0908354A2 true BRPI0908354A2 (en) 2019-09-24

Family

ID=41255642

Family Applications (1)

Application Number Title Priority Date Filing Date
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

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 (10)

* 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
WO2018046143A1 (en) * 2016-09-06 2018-03-15 Westinghouse Electric Sweden Ab 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
JP7349379B2 (en) * 2020-01-28 2023-09-22 三菱重工業株式会社 Fuel rod output analysis method, analysis device, and fuel rod output analysis program
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
CN117807777B (en) * 2023-12-27 2024-07-12 东北电力大学 Test piece design method for realizing axial non-uniform heating of nuclear reactor fuel rod

Family Cites Families (9)

* 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
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
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
US20050135547A1 (en) * 1998-03-11 2005-06-23 Wolfgang Schulz Control element for a nuclear reactor
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
LU90570B1 (en) * 2000-04-26 2001-10-29 Europ Economic Community Method of incineration of minor actinides in nuclear reactors
JP3508021B2 (en) * 2001-08-29 2004-03-22 株式会社原子力エンジニアリング Reactor core calculation method
DE10328920A1 (en) * 2003-06-26 2005-01-20 Framatome Anp Gmbh Method for mathematically modeling the core of a nuclear reactor

Also Published As

Publication number Publication date
WO2009134498A3 (en) 2009-12-30
KR20100115754A (en) 2010-10-28
JP2011528101A (en) 2011-11-10
ZA201005627B (en) 2011-06-29
EP2240939A4 (en) 2012-03-21
WO2009134498A2 (en) 2009-11-05
EP2240939A2 (en) 2010-10-20
TW200949856A (en) 2009-12-01
CN101946253A (en) 2011-01-12

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Legal Events

Date Code Title Description
B08F Application fees: dismissal - article 86 of industrial property law
B08K Lapse as no evidence of payment of the annual fee has been furnished to inpi (acc. art. 87)

Free format text: EM VIRTUDE DO ARQUIVAMENTO PUBLICADO NA RPI 2543 DE 01-10-2019 E CONSIDERANDO AUSENCIA DE MANIFESTACAO DENTRO DOS PRAZOS LEGAIS, INFORMO QUE CABE SER MANTIDO O ARQUIVAMENTO DO PEDIDO DE PATENTE, CONFORME O DISPOSTO NO ARTIGO 12, DA RESOLUCAO 113/2013.