ES8705676A1 - Gray rod for a nuclear reactor - Google Patents

Gray rod for a nuclear reactor

Info

Publication number
ES8705676A1
ES8705676A1 ES550274A ES550274A ES8705676A1 ES 8705676 A1 ES8705676 A1 ES 8705676A1 ES 550274 A ES550274 A ES 550274A ES 550274 A ES550274 A ES 550274A ES 8705676 A1 ES8705676 A1 ES 8705676A1
Authority
ES
Spain
Prior art keywords
pellets
longitudinal
section
longitudinal section
gray rod
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
ES550274A
Other languages
Spanish (es)
Other versions
ES550274A0 (en
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
Publication of ES8705676A1 publication Critical patent/ES8705676A1/en
Publication of ES550274A0 publication Critical patent/ES550274A0/en
Expired legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
    • G21C19/02—Details of handling arrangements
    • G21C19/08—Means for heating fuel elements before introduction into the core; Means for heating or cooling fuel elements after removal from the core
    • 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
    • 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
    • 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)
  • Devices And Processes Conducted In The Presence Of Fluids And Solid Particles (AREA)
  • Vibration Dampers (AREA)

Abstract

The invention relates to an improved gray rod for insertion in a nuclear fuel assembly having an array of fuel rods. The gray rod includes a thin-walled cladding tube (46) a first longitudinal section of which is positioned within, and a second longitudinal section of which is positioned essentially without, the array of fuel rods when the gray rod is inserted in the fuel assembly. The first longitudinal section defines a pellet-receiving space (52) having detained therein a stack of annular pellets (48) with an outer diameter sufficient to lend radial support to the wall of the first longitudinal tube section. The second longitudinal section defines a hollow space (54) devoid of pellets and having means to resist radial collapse under external pressure. This means may be a partially compressed spiral spring (50) which serves the dual purpose of retaining the stack of pellets (48) in the pellet-receiving space (52) and of lending radial support to the wall of the second longitudinal tube section or it may be holes through the wall to allow pressure equalisation (Fig. 6, not shown). The cladding tube is composed of stainless-steel material having a low neutron-capture cross- section, and the annular pellets preferably being composed of Zircaloy or Zirconia material.
ES550274A 1984-12-27 1985-12-20 Gray rod for a nuclear reactor Expired ES8705676A1 (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US68677184A 1984-12-27 1984-12-27

Publications (2)

Publication Number Publication Date
ES8705676A1 true ES8705676A1 (en) 1987-05-01
ES550274A0 ES550274A0 (en) 1987-05-01

Family

ID=24757677

Family Applications (1)

Application Number Title Priority Date Filing Date
ES550274A Expired ES8705676A1 (en) 1984-12-27 1985-12-20 Gray rod for a nuclear reactor

Country Status (8)

Country Link
JP (2) JPS61161488A (en)
KR (1) KR930011014B1 (en)
CN (1) CN85109308A (en)
BE (1) BE903946A (en)
ES (1) ES8705676A1 (en)
FR (1) FR2575580B1 (en)
GB (1) GB2169127B (en)
IT (1) IT1200904B (en)

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US7412021B2 (en) * 2005-07-26 2008-08-12 Westinghouse Electric Co Llc Advanced gray rod control assembly
CN109036591B (en) * 2017-06-08 2021-10-15 中广核工程有限公司 Nuclear reactor core

Family Cites Families (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
GB926133A (en) * 1958-10-28 1963-05-15 Atomic Energy Authority Uk Improvements in or relating to nuclear reactors
JPS5419089A (en) * 1977-07-12 1979-02-13 Toshiba Corp Method to make a reactor control rod
US4432934A (en) * 1980-12-16 1984-02-21 Westinghouse Electric Corp. Displacer rod for use in a mechanical spectral shift reactor
FR2518300B1 (en) * 1981-12-11 1987-10-16 Framatome Sa PENCIL CONTAINING CONSUMABLE MATERIAL FOR THE PILOTAGE OF A NUCLEAR REACTOR
ES291691Y (en) * 1983-11-30 1987-01-16 Westinghouse Electric Corporation AUXILIARY CONTROL ROD FOR FINE ADJUSTMENT OF THE REACTIVITY OF A NUCLEAR REACTOR
DE3534902A1 (en) * 1985-09-30 1987-04-02 Kraftwerk Union Ag Water displacing member

Also Published As

Publication number Publication date
KR860005394A (en) 1986-07-21
IT8523264A0 (en) 1985-12-18
FR2575580A1 (en) 1986-07-04
FR2575580B1 (en) 1989-12-08
GB2169127A (en) 1986-07-02
JPH079118Y2 (en) 1995-03-06
IT1200904B (en) 1989-01-27
GB2169127B (en) 1988-06-22
JPH0674998U (en) 1994-10-21
CN85109308A (en) 1986-08-06
GB8530483D0 (en) 1986-01-22
KR930011014B1 (en) 1993-11-19
ES550274A0 (en) 1987-05-01
BE903946A (en) 1986-06-24
JPS61161488A (en) 1986-07-22

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Legal Events

Date Code Title Description
FD1A Patent lapsed

Effective date: 20050310