FR1487567A - Réacteur nucléaire présentant des tubes verticaux - Google Patents

Réacteur nucléaire présentant des tubes verticaux

Info

Publication number
FR1487567A
FR1487567A FR70367A FR70367A FR1487567A FR 1487567 A FR1487567 A FR 1487567A FR 70367 A FR70367 A FR 70367A FR 70367 A FR70367 A FR 70367A FR 1487567 A FR1487567 A FR 1487567A
Authority
FR
France
Prior art keywords
nuclear reactor
vertical tubes
tubes
vertical
nuclear
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
FR70367A
Other languages
English (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.)
UK Atomic Energy Authority
Original Assignee
UK Atomic Energy Authority
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 UK Atomic Energy Authority filed Critical UK Atomic Energy Authority
Application granted granted Critical
Publication of FR1487567A publication Critical patent/FR1487567A/fr
Expired legal-status Critical Current

Links

Classifications

    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C1/00—Reactor types
    • G21C1/04—Thermal reactors ; Epithermal reactors
    • G21C1/06—Heterogeneous reactors, i.e. in which fuel and moderator are separated
    • G21C1/14—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor
    • G21C1/16—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor, sodium-heavy water reactor or organic coolant-heavy water reactor
    • G21C1/18—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor, sodium-heavy water reactor or organic coolant-heavy water reactor coolant being pressurised
    • G21C1/20—Heterogeneous reactors, i.e. in which fuel and moderator are separated moderator being substantially not pressurised, e.g. swimming-pool reactor moderator and coolant being different or separated, e.g. sodium-graphite reactor, sodium-heavy water reactor or organic coolant-heavy water reactor coolant being pressurised moderator being liquid, e.g. pressure-tube reactor
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/02—Fuel elements
    • G21C3/04—Constructional details
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
    • G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C3/00—Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/30—Assemblies of a number of fuel elements in the form of a rigid unit
    • G21C3/32—Bundles of parallel pin-, rod-, or tube-shaped fuel elements
    • G21C3/34—Spacer grids
    • G21C3/344—Spacer grids formed of assembled tubular elements
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C5/00—Moderator or core structure; Selection of materials for use as moderator
    • G21C5/02—Details
    • G21C5/06—Means for locating or supporting fuel elements
    • 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)
FR70367A 1965-07-22 1966-07-21 Réacteur nucléaire présentant des tubes verticaux Expired FR1487567A (fr)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
GB5234/66A GB1148507A (en) 1965-07-22 1965-07-22 Nuclear reactors
GB173966 1966-01-13

Publications (1)

Publication Number Publication Date
FR1487567A true FR1487567A (fr) 1967-07-07

Family

ID=26236944

Family Applications (1)

Application Number Title Priority Date Filing Date
FR70367A Expired FR1487567A (fr) 1965-07-22 1966-07-21 Réacteur nucléaire présentant des tubes verticaux

Country Status (3)

Country Link
US (1) US3425905A (fr)
FR (1) FR1487567A (fr)
GB (1) GB1148507A (fr)

Families Citing this family (8)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3619367A (en) * 1967-06-06 1971-11-09 Commissariat Energie Atomique Fuel assembly with solid end-fitting
FR2274995B1 (fr) * 1974-06-12 1977-01-07 Commissariat Energie Atomique Chandelle support d'assemblage combustible pour sommier de reacteur nucleaire
US4313797A (en) * 1979-09-19 1982-02-02 The Babcock & Wilcox Company Guide tube sleeve
US4376092A (en) * 1979-12-10 1983-03-08 Westinghouse Electric Corp. Nuclear fuel assembly wear sleeve
FR2513797A1 (fr) * 1981-09-30 1983-04-01 Commissariat Energie Atomique Dispositif de protection neutronique superieure pour assemblage de reacteur nucleaire
US4543233A (en) * 1982-04-08 1985-09-24 The United States Of America As Represented By The United States Department Of Energy Mechanically attached load pad for liquid metal nuclear reactor fuel assemblies
US4857264A (en) * 1986-11-03 1989-08-15 Westinghouse Electric Corp. Frictionally loaded top end supports for cantilever-mounted rod guides of a pressurized water reactor
US7995701B2 (en) * 2008-05-21 2011-08-09 Westinghouse Electric Company Llc Nuclear core component hold-down assembly

Family Cites Families (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2926127A (en) * 1957-03-25 1960-02-23 Willard H Mccorkle Neutronic reactor with accessible thimble and emergency cooling features
NL278891A (fr) * 1961-05-27
NL279325A (fr) * 1961-06-06
BE632489A (fr) * 1962-06-13 1900-01-01
US3226301A (en) * 1962-10-03 1965-12-28 Euratom Heterogeneous nuclear reactor liquid moderated and cooled
GB1051162A (fr) * 1963-05-31 1966-12-14

Also Published As

Publication number Publication date
GB1148507A (en) 1969-04-16
US3425905A (en) 1969-02-04

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