GB1126396A - Nuclear reactor fuel element and method of manufacturing same - Google Patents

Nuclear reactor fuel element and method of manufacturing same

Info

Publication number
GB1126396A
GB1126396A GB28965/67A GB2896567A GB1126396A GB 1126396 A GB1126396 A GB 1126396A GB 28965/67 A GB28965/67 A GB 28965/67A GB 2896567 A GB2896567 A GB 2896567A GB 1126396 A GB1126396 A GB 1126396A
Authority
GB
United Kingdom
Prior art keywords
per cent
interlayer
core
outer sheath
alloy
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
GB28965/67A
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.)
Atomic Energy of Canada Ltd AECL
Original Assignee
Atomic Energy of Canada Ltd AECL
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 Atomic Energy of Canada Ltd AECL filed Critical Atomic Energy of Canada Ltd AECL
Publication of GB1126396A publication Critical patent/GB1126396A/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
    • G21C3/42Selection of substances for use as reactor fuel
    • G21C3/58Solid reactor fuel Pellets made of fissile material
    • G21C3/60Metallic fuel; Intermetallic dispersions
    • 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
    • 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
    • G21C3/16Details of the construction within the casing
    • G21C3/20Details of the construction within the casing with coating on fuel or on inside of casing; with non-active interlayer between casing and active material with multiple casings or multiple active layers
    • 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

Abstract

1,126,396. Fuel elements. ATOMIC ENERGY OF CANADA Ltd. 22 June, 1967 [18 July, 1966], No. 28965/67. Heading G6C. A fuel element comprises a core 10 of nuclear metal fuel with a void space 11 surrounded by a sheathing assembly consisting of inner and outer sheaths 12, 14 separated by and in contact with a continuous ductile interlayer 13. The core 10 is preferably formed from U metal having minor alloying additions to reduce swelling upon irradiation. The U may contain up to 1.5 wt. per cent of any of Fe, C, Cr or Si either individually or in combination and should be heat treated by being beta quenched from about 750‹ C. and annealed at about 550‹ C. for several hours to produce a fine grained randomly oriented structure containing a fine precipitate. Other U alloys which may be used contain up to 10 wt. per cent Zr or Al, or up to 1 wt. per cent Mo or Nb. The void volume is between 2 and 15%, preferably about 5% of the U volume. Natural or enriched U, or alternatively other fuel metals and their alloys such as Pu, Th, Pu-U, Th-U may be used. The inner and outer sheaths 12, 14 are formed from a corrosion-resistant Zr alloy, preferably Zircaloy-2, with Zircaloy-4 and Zr containing about 2À5 wt. per cent Nb also being suitable. Circumstances may occur in which stainless steel or a Ni-Cr alloy is suitable for the sheaths. The preferred material for the interlayer 13 is extremely ductile material formed by alloying A1 with from 0 to 25 wt. per cent U, preferably about 10 wt. per cent. The U alloy provides a monitoring signal on fracture of the outer sheath 14. A non-fissile material such as Pb or a ductile alloy may, however, also be used for the interlayer 13. The end cap assemblies each consist of two portions 15, 16, portion 16 being welded to the inner sheath 12 and portion 15 to the outer sheath 14. The fuel element is fabricated by: (a) co-extrusion of the core 10 and the inner sheath 12 followed by slip fit assembly inside the interlayer 13 and the outer sheath 14, the outer sheath then being reduced in diameter by swaging or drawing to provide intimate contact between the layers, (b) individual fabrication of the component parts and slip fit assembly followed by swaging or drawing, or (c) assembly of the core 10 and the inner sheath 12 by co-extrusion or slip fit assembly followed by extrusion cladding of the interlayer 13, the assembly so produced then being slip fitted into the outer sheath 14.
GB28965/67A 1966-07-18 1967-06-22 Nuclear reactor fuel element and method of manufacturing same Expired GB1126396A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
CA965709 1966-07-18

Publications (1)

Publication Number Publication Date
GB1126396A true GB1126396A (en) 1968-09-05

Family

ID=4142594

Family Applications (1)

Application Number Title Priority Date Filing Date
GB28965/67A Expired GB1126396A (en) 1966-07-18 1967-06-22 Nuclear reactor fuel element and method of manufacturing same

Country Status (1)

Country Link
GB (1) GB1126396A (en)

Cited By (9)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2290733A1 (en) * 1974-11-11 1976-06-04 Gen Electric COMPOSITE SHEATH FOR FUEL ELEMENT
FR2399713A1 (en) * 1977-08-01 1979-03-02 Gen Electric PERFECTED NUCLEAR FUEL ELEMENT AND METHOD TO PREVENT STRESS CRACKING OF THE SHEATH
US5991354A (en) * 1996-01-30 1999-11-23 Siemens Power Corporation Nuclear fuel pellet
US6002735A (en) * 1996-01-30 1999-12-14 Siemens Power Corporation Nuclear fuel pellet
WO2011143172A1 (en) * 2010-05-11 2011-11-17 Thorium Power, Inc. Fuel assembly with metal fuel alloy kernel and method of manufacturing thereof
US8654917B2 (en) 2007-12-26 2014-02-18 Thorium Power, Inc. Nuclear reactor (alternatives), fuel assembly of seed-blanket subassemblies for nuclear reactor (alternatives), and fuel element for fuel assembly
US9355747B2 (en) 2008-12-25 2016-05-31 Thorium Power, Inc. Light-water reactor fuel assembly (alternatives), a light-water reactor, and a fuel element of fuel assembly
US10170207B2 (en) 2013-05-10 2019-01-01 Thorium Power, Inc. Fuel assembly
US10192644B2 (en) 2010-05-11 2019-01-29 Lightbridge Corporation Fuel assembly

Cited By (19)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US4045288A (en) * 1974-11-11 1977-08-30 General Electric Company Nuclear fuel element
FR2290733A1 (en) * 1974-11-11 1976-06-04 Gen Electric COMPOSITE SHEATH FOR FUEL ELEMENT
FR2399713A1 (en) * 1977-08-01 1979-03-02 Gen Electric PERFECTED NUCLEAR FUEL ELEMENT AND METHOD TO PREVENT STRESS CRACKING OF THE SHEATH
US5991354A (en) * 1996-01-30 1999-11-23 Siemens Power Corporation Nuclear fuel pellet
US6002735A (en) * 1996-01-30 1999-12-14 Siemens Power Corporation Nuclear fuel pellet
US8654917B2 (en) 2007-12-26 2014-02-18 Thorium Power, Inc. Nuclear reactor (alternatives), fuel assembly of seed-blanket subassemblies for nuclear reactor (alternatives), and fuel element for fuel assembly
US9355747B2 (en) 2008-12-25 2016-05-31 Thorium Power, Inc. Light-water reactor fuel assembly (alternatives), a light-water reactor, and a fuel element of fuel assembly
EA023017B1 (en) * 2010-05-11 2016-04-29 Ториум Пауэр, Инк. Fuel assembly
WO2011143293A1 (en) * 2010-05-11 2011-11-17 Thorium Power, Inc. Fuel assembly
WO2011143172A1 (en) * 2010-05-11 2011-11-17 Thorium Power, Inc. Fuel assembly with metal fuel alloy kernel and method of manufacturing thereof
EP3038112A1 (en) * 2010-05-11 2016-06-29 Thorium Power, Inc. Fuel assembly
US10037823B2 (en) 2010-05-11 2018-07-31 Thorium Power, Inc. Fuel assembly
US10192644B2 (en) 2010-05-11 2019-01-29 Lightbridge Corporation Fuel assembly
US10991473B2 (en) 2010-05-11 2021-04-27 Thorium Power, Inc. Method of manufacturing a nuclear fuel assembly
US11195629B2 (en) 2010-05-11 2021-12-07 Thorium Power, Inc. Fuel assembly
US11837371B2 (en) 2010-05-11 2023-12-05 Thorium Power, Inc. Method of manufacturing a nuclear fuel assembly
US11862353B2 (en) 2010-05-11 2024-01-02 Thorium Power, Inc. Fuel assembly
US10170207B2 (en) 2013-05-10 2019-01-01 Thorium Power, Inc. Fuel assembly
US11211174B2 (en) 2013-05-10 2021-12-28 Thorium Power, Inc. Fuel assembly

Similar Documents

Publication Publication Date Title
US5341407A (en) Inner liners for fuel cladding having zirconium barriers layers
US5373541A (en) Nuclear fuel rod and method of manufacturing the cladding of such a rod
US5026516A (en) Corrosion resistant cladding for nuclear fuel rods
KR970004349B1 (en) Fuel rod for a nuclear reactor fuel assembly
JPH01267493A (en) Fuel element having acid resisting cover
EP0192405B1 (en) Nuclear fuel claddings
GB1525615A (en) Nuclear fuel elements
US3442761A (en) Nuclear reactor fuel element
EP0399222A1 (en) Corrosion resistant zirconium alloys containing copper, nickel and iron
GB1126396A (en) Nuclear reactor fuel element and method of manufacturing same
DE19509257B4 (en) Improved zirconium alloy nuclear fuel sheath
US5618356A (en) Method of fabricating zircaloy tubing having high resistance to crack propagation
KR100284643B1 (en) Zirconium tin iron alloys for nuclear fuel rods and structural parts for high burnup
KR100284208B1 (en) Method of manufacturing zirconium tin iron alloys for nuclear fuel rods and structural parts for high burnup
US5190721A (en) Zirconium-bismuth-niobium alloy for nuclear fuel cladding barrier
DE1202985B (en) Zirconium alloy
US4613479A (en) Water reactor fuel cladding
US20020061089A1 (en) Fuel element for a pressurized water reactor and method for producing cladding tubes
EP0287875B1 (en) Zirconium cladded pressurized water reactor nuclear fuel element
US3331748A (en) Nuclear fuel elements
US5805656A (en) Fuel channel and fabrication method therefor
EP0893800A1 (en) Pressurized water reactor nuclear fuel assembly
US3215607A (en) Multi-region neutronic fuel element
DE1807945C3 (en) Radioactive source for heat generation
US4933136A (en) Water reactor fuel cladding