ATE345570T1 - Verfahren und einrichtung zur bewertung der integrität einer steuersubstanz in einer nuklearanlage - Google Patents

Verfahren und einrichtung zur bewertung der integrität einer steuersubstanz in einer nuklearanlage

Info

Publication number
ATE345570T1
ATE345570T1 AT02759042T AT02759042T ATE345570T1 AT E345570 T1 ATE345570 T1 AT E345570T1 AT 02759042 T AT02759042 T AT 02759042T AT 02759042 T AT02759042 T AT 02759042T AT E345570 T1 ATE345570 T1 AT E345570T1
Authority
AT
Austria
Prior art keywords
integrity
value
fluid
nuclear plant
control rod
Prior art date
Application number
AT02759042T
Other languages
English (en)
Inventor
Lembit Sihver
Kurt-Ake Magnusson
Bjoern Bjurman
Original Assignee
Westinghouse Electric Sweden
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 Sweden filed Critical Westinghouse Electric Sweden
Application granted granted Critical
Publication of ATE345570T1 publication Critical patent/ATE345570T1/de

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C17/00—Monitoring; Testing ; Maintaining
    • G21C17/02—Devices or arrangements for monitoring coolant or moderator
    • G21C17/04—Detecting burst slugs
    • 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

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
AT02759042T 2001-08-23 2002-08-22 Verfahren und einrichtung zur bewertung der integrität einer steuersubstanz in einer nuklearanlage ATE345570T1 (de)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
SE0102813A SE520391C2 (sv) 2001-08-23 2001-08-23 Förfarande och anordning för utvärdering av integriteten av en styrsubstans i en nukleär anläggning

Publications (1)

Publication Number Publication Date
ATE345570T1 true ATE345570T1 (de) 2006-12-15

Family

ID=20285110

Family Applications (1)

Application Number Title Priority Date Filing Date
AT02759042T ATE345570T1 (de) 2001-08-23 2002-08-22 Verfahren und einrichtung zur bewertung der integrität einer steuersubstanz in einer nuklearanlage

Country Status (7)

Country Link
US (1) US20050013399A1 (de)
EP (1) EP1419508B1 (de)
AT (1) ATE345570T1 (de)
DE (1) DE60216120T2 (de)
ES (1) ES2275901T3 (de)
SE (1) SE520391C2 (de)
WO (1) WO2003021605A1 (de)

Families Citing this family (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN110600151A (zh) * 2019-09-19 2019-12-20 中国核动力研究设计院 一种适用于含氚氦气回路的实验室支持系统
CN112735613A (zh) * 2019-10-28 2021-04-30 中核核电运行管理有限公司 一种国产核燃料组件完整性跟踪监督方法
JP7470659B2 (ja) 2021-04-28 2024-04-18 三菱重工業株式会社 評価方法、評価システム及びプログラム
JP7507727B2 (ja) * 2021-05-13 2024-06-28 三菱重工業株式会社 評価方法、評価システム及びプログラム

Family Cites Families (16)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3103479A (en) * 1963-09-10 Nuclear reactor control rods
US3632470A (en) * 1968-05-15 1972-01-04 Gen Electric Reactor fuel leak detection
US4107533A (en) * 1976-10-20 1978-08-15 Hitachi, Ltd. Apparatus for measuring a concentration of radioactivity
SE414685B (sv) * 1977-05-06 1980-08-11 Asea Atom Ab Forfarande vid sokning och identifiering av en brenslepatron innehallande en brenslestav med leckande kapsel
JPS5793272A (en) * 1980-12-01 1982-06-10 Hitachi Ltd Radioactivity monitor
US4609524A (en) * 1983-11-16 1986-09-02 Westinghouse Electric Corp. Nuclear reactor component rods and method of forming the same
FR2569041B1 (fr) * 1984-08-08 1987-01-02 Fragema Framatome & Cogema Procede et dispositif de controle par ressuage de l'etancheite des gaines d'un assemblage de combustible nucleaire
JPS626200A (ja) * 1985-07-03 1987-01-13 株式会社東芝 制御棒破損検出装置
US4764335A (en) * 1987-03-02 1988-08-16 The United States Of America As Represented By The United States Department Of Energy Method and apparatus for diagnosing breached fuel elements
US4978506A (en) * 1988-05-18 1990-12-18 Westinghouse Electric Corp. Corrosion product monitoring method and system
US5126100A (en) * 1990-12-26 1992-06-30 Westinghouse Electric Corp. System for qualification of chemical decontamination methods for decontamination of nuclear reactor systems
US5524032A (en) * 1993-07-14 1996-06-04 General Electric Company Nuclear fuel cladding having an alloyed zirconium barrier layer
US5537450A (en) * 1994-01-31 1996-07-16 Radiological & Chemical Technology, Inc. On-line analysis of fuel integrity
SE509116C2 (sv) * 1997-04-16 1998-12-07 Asea Atom Ab Anordning för detektering av ädelgaser i avgaser från en kärnreaktor
USH1753H (en) * 1997-04-29 1998-10-06 The United States Of America As Represented By The United States Department Of Energy Pin and cermet hybrid bimodal reactor
SE514184C2 (sv) * 1997-11-21 2001-01-22 Asea Atom Ab Förfarande och anordning för utvärdering av integriteten hos kärnbränslet i en nukleär anläggning

Also Published As

Publication number Publication date
US20050013399A1 (en) 2005-01-20
ES2275901T3 (es) 2007-06-16
DE60216120D1 (de) 2006-12-28
EP1419508A1 (de) 2004-05-19
SE0102813L (sv) 2003-02-24
EP1419508B1 (de) 2006-11-15
WO2003021605A1 (en) 2003-03-13
SE520391C2 (sv) 2003-07-01
DE60216120T2 (de) 2007-09-27
SE0102813D0 (sv) 2001-08-23

Similar Documents

Publication Publication Date Title
Ozaki et al. Drift-flux model for rod bundle geometry
KR101708168B1 (ko) 3차원 전산유체해석 기반의 배관 감육 예측 및 평가 장치 및 그 방법
ATE345570T1 (de) Verfahren und einrichtung zur bewertung der integrität einer steuersubstanz in einer nuklearanlage
KR890016579A (ko) 가압수형 원자로의 전력 복귀능력의 결정 및 계산방법
SE9704286L (sv) Förfarande och anordning för utvärdering av integriteten hos kärnbränslet i en nukleär anläggning
Bernard et al. Fatigue Crack Growth Curve in Air Environment at 300° C for Stainless Steels
ATE526670T1 (de) Verfahren zum betrieb eines reaktors einer nuklearanlage
Dewees et al. A continued evaluation of the role of material hardening behavior for the net TG1 and TG4 specimens
Bläsius et al. Quality management, verification, and validation of structure mechanical computer codes at GRS
Micallef Crack control in base-restrained reinforced concrete walls
Solin et al. Fatigue of stainless steel in simulated operational conditions: effects of PWR water, temperature and holds
Kerezsi et al. Using the ASME and BSI codes to predict crack growth due to repeated thermal shock
Reese et al. Numerical Evaluation of Environmentally Assisted Fatigue (EAF) in Consideration of Recent Updates of the Formulas and Hold Time Effects
Orynyak et al. Methodological features of WWER RPV metal critical temperature of brittleness prediction on the base of the data scatter and the chemical composition
RU2300819C2 (ru) Способ контроля герметичности парогенератора судовой ядерной энергетической установки
Tcherner et al. Candu energy experience in condition assessment of nuclear safety related concrete structures
Kordisch et al. Application of material models and assessment of strains in a surgeline under cyclic thermal loading
Lewis et al. Supersomite--a Large Test Facility for the Study of Thermal Striping in Liquid Metal Fast Breeder Reactors
Ma Cement paste degradation under external sulfate attack: an experimental and numerical research
Cronvall Long-Term Operation of BWR RPV and Its Internals: Article PVP2018-84541
Keim et al. European Project on Structural Integrity STYLE: Project Status
Arzhaev et al. Leak-before-break criteria and strength monitoring implementation impact on in-service inspection of RBMK primary circuit components
Yu et al. Extended applications of LBB piping evaluation diagrams for a new plant design
Sommerville Boiling Water Reactor Recirculation Line Break Acoustic Loads: A Bounding Approach
Smeekes et al. Piping vibration management combining measurements and numerical simulation

Legal Events

Date Code Title Description
RER Ceased as to paragraph 5 lit. 3 law introducing patent treaties