GB1121979A - An annular fuel element for a nuclear reactor - Google Patents

An annular fuel element for a nuclear reactor

Info

Publication number
GB1121979A
GB1121979A GB24502/67A GB2450267A GB1121979A GB 1121979 A GB1121979 A GB 1121979A GB 24502/67 A GB24502/67 A GB 24502/67A GB 2450267 A GB2450267 A GB 2450267A GB 1121979 A GB1121979 A GB 1121979A
Authority
GB
United Kingdom
Prior art keywords
cladding
fuel
plugs
external
zircaloy
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
GB24502/67A
Inventor
Robert Fuhrmann
Marcel Michel
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.)
Commissariat a lEnergie Atomique et aux Energies Alternatives CEA
Original Assignee
Commissariat a lEnergie Atomique CEA
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 Commissariat a lEnergie Atomique CEA filed Critical Commissariat a lEnergie Atomique CEA
Publication of GB1121979A publication Critical patent/GB1121979A/en
Expired legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/02Fuel elements
    • G21C3/04Constructional details
    • G21C3/06Casings; Jackets
    • G21C3/10End closures ; Means for tight mounting therefor
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/02Fuel elements
    • G21C3/04Constructional details
    • G21C3/06Casings; Jackets
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/02Fuel elements
    • G21C3/04Constructional details
    • G21C3/06Casings; Jackets
    • G21C3/08Casings; Jackets provided with external means to promote heat-transfer, e.g. fins, baffles
    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/38Fuel units consisting of a single fuel element in a supporting sleeve or in another supporting element
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Physics & Mathematics (AREA)
  • Engineering & Computer Science (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Butt Welding And Welding Of Specific Article (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)

Abstract

1,121,979. Fuel elements. COMMISSARIAT A L'ENERGIE ATOMIQUE. 26 May, 1967 [27 May, 1966], No. 24502/67. Heading G6C. An annular fuel element for a natural uranium reactor cooled by circulation of CO 2 gas in the same direction inside and outside the element comprises a tubular slug of nuclear fuel covered with external and internal cladding, both of which have fins arranged in chevrons and are connected by annular plugs, the external cladding and plugs being made from a Mg-based alloy and the internal cladding from Zr or a Zr-based alloy having a higher hot strength than the Mg alloy. Suitable Zr alloys are Zircaloy ATR (containing, by wt., 0À5% Cu and 0À5% Mo), Zircaloy AJR (containing, by wt., 1% Cu and 1À5% Mo) and Zircaloy-2 (containing, by wt., 1À5% Sn and small additions of Ni, Cr and Fe). The fins on the internal cladding are preferably shallower than those on the external cladding. The external cladding may also have longitudinal partitions for centering the fuel element in a coolant duct. An annular disc of thermally insulating material resistant to creep when hot (e.g. a ceramic) is interposed between each plug and the fuel. The fuel is covered with the cladding members which are then forced against the fuel by any suitable method, e.g. hydraulic cladding after temporary plugging. The permanent plugs are then attached. The cladding members are preferably anchored on circular grooves in the fuel to prevent a ratchet effect during thermal cycling. The plugs are joined to the external cladding by arc-welding in an argon atmosphere or by electron beam welding and to the internal cladding by a process similar to that described in Specification 1,099,025.
GB24502/67A 1966-05-27 1967-05-26 An annular fuel element for a nuclear reactor Expired GB1121979A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR63325A FR1499999A (en) 1966-05-27 1966-05-27 annular fuel element

Publications (1)

Publication Number Publication Date
GB1121979A true GB1121979A (en) 1968-07-31

Family

ID=8609660

Family Applications (1)

Application Number Title Priority Date Filing Date
GB24502/67A Expired GB1121979A (en) 1966-05-27 1967-05-26 An annular fuel element for a nuclear reactor

Country Status (6)

Country Link
BE (1) BE698106A (en)
CH (1) CH474123A (en)
ES (1) ES341051A1 (en)
FR (1) FR1499999A (en)
GB (1) GB1121979A (en)
LU (1) LU53739A1 (en)

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
RU2794744C1 (en) * 2022-05-04 2023-04-24 Акционерное общество "Электрогорский научно-исследовательский центр по безопасности атомных электростанций" Method for increating critical heat fluxes in a fuel assembly with tubular fuel rods

Cited By (1)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
RU2794744C1 (en) * 2022-05-04 2023-04-24 Акционерное общество "Электрогорский научно-исследовательский центр по безопасности атомных электростанций" Method for increating critical heat fluxes in a fuel assembly with tubular fuel rods

Also Published As

Publication number Publication date
CH474123A (en) 1969-06-15
LU53739A1 (en) 1967-07-24
BE698106A (en) 1967-10-16
ES341051A1 (en) 1968-12-16
FR1499999A (en) 1967-11-03

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