CA968470A - Nuclear reactor internals construction and failed fuel rod detection system - Google Patents

Nuclear reactor internals construction and failed fuel rod detection system

Info

Publication number
CA968470A
CA968470A CA159,318A CA159318A CA968470A CA 968470 A CA968470 A CA 968470A CA 159318 A CA159318 A CA 159318A CA 968470 A CA968470 A CA 968470A
Authority
CA
Canada
Prior art keywords
construction
detection system
nuclear reactor
fuel rod
rod detection
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.)
Expired
Application number
CA159,318A
Other languages
English (en)
Other versions
CA159318S (en
Inventor
Erling Frisch
Harry N. Andrews
Current Assignee (The listed assignees may be inaccurate. Google has not performed a legal analysis and makes no representation or warranty as to the accuracy of the list.)
CBS Corp
Original Assignee
Westinghouse Electric Corp
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 Corp filed Critical Westinghouse Electric Corp
Application granted granted Critical
Publication of CA968470A publication Critical patent/CA968470A/en
Expired legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C7/00—Control of nuclear reaction
    • G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
    • G21C7/08—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section by displacement of solid control elements, e.g. control rods
    • G21C7/10—Construction of control elements
    • G21C7/117—Clusters of control rods; Spider construction
    • 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)
  • Chemical & Material Sciences (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
CA159,318A 1972-01-21 1972-12-18 Nuclear reactor internals construction and failed fuel rod detection system Expired CA968470A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US00219781A US3817829A (en) 1972-01-21 1972-01-21 Nuclear reactor internals construction and failed fuel rod detection system

Publications (1)

Publication Number Publication Date
CA968470A true CA968470A (en) 1975-05-27

Family

ID=22820754

Family Applications (1)

Application Number Title Priority Date Filing Date
CA159,318A Expired CA968470A (en) 1972-01-21 1972-12-18 Nuclear reactor internals construction and failed fuel rod detection system

Country Status (11)

Country Link
US (1) US3817829A (de)
JP (1) JPS5322237B2 (de)
BE (1) BE794342A (de)
CA (1) CA968470A (de)
CH (1) CH563649A5 (de)
DE (1) DE2301730A1 (de)
ES (1) ES410422A1 (de)
FR (1) FR2168564B1 (de)
GB (1) GB1364770A (de)
IT (1) IT978290B (de)
SE (1) SE7300876L (de)

Families Citing this family (24)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
DE2310080A1 (de) * 1973-02-28 1974-08-29 Siemens Ag Siedewasserreaktor
US4092216A (en) * 1973-12-14 1978-05-30 Commissariat A L'energie Atomique Nuclear reactor
AT369179B (de) * 1974-04-10 1982-12-10 Kraftwerk Union Ag Loesbare durchfuehrung in einem reaktordruckbehaelter
JPS52104691A (en) * 1976-02-27 1977-09-02 Toshiba Corp Detecting apparatsu for nuclear fuel injury inside reactor
US4173513A (en) * 1977-07-07 1979-11-06 Westinghouse Electric Corp. Nuclear reactor with control rods
US4231843A (en) * 1977-08-02 1980-11-04 Westinghouse Electric Corp. Guide tube flow diffuser
FR2411469A1 (fr) * 1977-12-09 1979-07-06 Leleu Sa Marcel Procede de fabrication d'un guide de grappe pour reacteur nucleaire et outillage pour la mise en oeuvre de ce procede
CH627297A5 (de) * 1978-06-09 1981-12-31 Sulzer Ag
CH631673A5 (de) * 1978-08-17 1982-08-31 Sulzer Ag Gestell zum zwischenlagern von brennelement-buendeln.
FR2475781A1 (fr) * 1980-02-08 1981-08-14 Framatome Sa Ensemble de commande d'un reacteur nucleaire
US4788033A (en) * 1983-04-29 1988-11-29 Westinghouse Electric Corp. Calandria
FR2558983B1 (fr) * 1984-01-30 1986-06-20 Framatome Sa Dispositif de pilotage du coeur d'un reacteur nucleaire
DE3564507D1 (en) * 1984-03-30 1988-09-22 Westinghouse Electric Corp Control rod spider assembly for a nuclear reactor fuel assembly
US4707331A (en) * 1985-11-14 1987-11-17 Westinghouse Electric Corp. Top end support for water displacement rod guides of pressurized water reactor
US4752433A (en) * 1985-12-09 1988-06-21 Westinghouse Electric Corp. Vent system for displacer rod drive mechanism of pressurized water reactor and method of operation
FR2627317B1 (fr) * 1988-02-15 1990-07-27 Framatome Sa Equipements internes superieurs de reacteur nucleaire, a dispositifs de guidage de grappes
FR2637410B1 (fr) * 1988-10-04 1990-11-02 Framatome Sa Dispositif de centrage et de fixation d'une bride de guide de grappe sur une plaque de coeur d'un reacteur nucleaire
EP0363710A3 (de) * 1988-10-14 1990-08-22 Westinghouse Electric Corporation Kombinierte Stützsäule und Führungsrohr zur Anwendung in einem Kernreaktor
US5098647A (en) * 1990-07-16 1992-03-24 Westinghouse Electric Corp. Guide tube insert assembly for use in a nuclear reactor
US5108694A (en) * 1991-08-23 1992-04-28 Westinghouse Electric Corp. Power distribution measuring system employing gamma detectors outside of nuclear reactor vessel
US5345479A (en) * 1993-03-17 1994-09-06 Westinghouse Electric Corporation Sensitivity enhancement for airborne radioactivity monitoring system to detect reactor coolant leaks
SE532185C2 (sv) * 2007-04-10 2009-11-10 Westinghouse Electric Sweden Förfarande för att driva en reaktor hos en kärnanläggning
CN101770822B (zh) * 2008-12-31 2012-08-08 中国核动力研究设计院 管束式对星形架全行程连续导向组件
CN111799003A (zh) * 2020-06-05 2020-10-20 江苏核电有限公司 一种定位破损燃料组件的方法

Also Published As

Publication number Publication date
GB1364770A (en) 1974-08-29
JPS5322237B2 (de) 1978-07-07
BE794342A (fr) 1973-07-19
US3817829A (en) 1974-06-18
IT978290B (it) 1974-09-20
JPS4882295A (de) 1973-11-02
SE7300876L (de) 1973-07-23
FR2168564A1 (de) 1973-08-31
ES410422A1 (es) 1976-08-01
CH563649A5 (de) 1975-06-30
FR2168564B1 (de) 1978-10-27
DE2301730A1 (de) 1973-07-26

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