GB1251400A - - Google Patents

Info

Publication number
GB1251400A
GB1251400A GB1251400DA GB1251400A GB 1251400 A GB1251400 A GB 1251400A GB 1251400D A GB1251400D A GB 1251400DA GB 1251400 A GB1251400 A GB 1251400A
Authority
GB
United Kingdom
Prior art keywords
alloy
rod
billet
core
heat
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
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 filed Critical
Publication of GB1251400A publication Critical patent/GB1251400A/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
    • G21C21/00Apparatus or processes specially adapted to the manufacture of reactors or parts thereof
    • G21C21/02Manufacture of fuel elements or breeder elements contained in non-active casings
    • G21C21/16Manufacture of fuel elements or breeder elements contained in non-active casings by casting or dipping techniques
    • 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

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Chemical & Material Sciences (AREA)
  • Dispersion Chemistry (AREA)
  • Manufacturing & Machinery (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Heat Treatment Of Articles (AREA)
  • Manufacture And Refinement Of Metals (AREA)

Abstract

1,251,400. Fuel elements. ATOMIC ENERGY OF CANADA Ltd. 23 May, 1969 [4 June, 1968 (2)], No. 26568/69. Addition to 1,118,850. Heading G6C. A fuel element comprises a core of U metal alloyed with from 2 to 7À3 wt. per cent Si, the core containing one or more void spaces, and a sheath of corrosion resistant alloy, e.g. Zr alloy. The core is heat-treated so as to form a corrosion-resistant alloy, preferably the delta phase U 3 Si. The total volume of the void space(s) is between 3 and 25%, preferably 15%, of that of the U-Si alloy, its purpose being to accommodate any swelling of the alloy and also the fission products produced. The fuel element is fabricated by one of the following methods: (a) casting the U-Si alloy in the form of a rod having a central void, heat-treating the rod at 750‹ to 900‹ C. for 2 to 300 hours to peritectoidally transform the alloy to the delta (U 3 Si) form, machining the rod to predetermined dimensions, and slip fitting the rod into a protective sheath; (b) casting the U-Si alloy in the form of a billet, heat-treating the billet at 750‹ to 900‹ C. for 2 to 300 hours to peritectoidally transform the alloy to the delta phase, extruding the billet at less than 930‹ C.(the peritectoid temperature) such that a void is formed in the rod, machining the rod to predetermined dimensions, and slip fitting the rod into a protective sheath; (c), as (b) above, but extruding the billet before the heat-treatment; (d) casting the U-Si alloy in the form of a billet, heat-treating the billet at 750‹ to 900‹ C. for 2 to 300 hours to peritectoidally transform the alloy to the delta phase, and co-extruding the billet inside a corrosionresistant sheath at less than 930‹ C. to form a U 3 Si core having a central void; and (e), as (d) above, but co-extruding the billet before the heat-treatment. A plug of U 3 Si may be bonded to one or both ends of the core so that the void is enclosed by the core. The U-Si alloy may alternatively be cast as a rod having a uniformly dispersed porosity produced by the introduction of an inert gas, e.g. helium, as by bubbling the gas through the molten alloy or exposing the molten alloy, typically at 1500‹ C., to an atmosphere of the inert gas so that sufficient of the inert gas is absorbed by the alloy, or by placing a gas-generating liquid or solid, e.g. magnesium, in the mould cavity in which the core is to be formed. The rod is heat-treated as in method (a) above to transform it peritectoidally to the delta phase and then machined to its final dimensions before being slip fitted into a protective sheath.
GB1251400D 1968-06-04 1969-05-23 Expired GB1251400A (en)

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
US73422168A 1968-06-04 1968-06-04
US73424068A 1968-06-04 1968-06-04

Publications (1)

Publication Number Publication Date
GB1251400A true GB1251400A (en) 1971-10-27

Family

ID=27112696

Family Applications (1)

Application Number Title Priority Date Filing Date
GB1251400D Expired GB1251400A (en) 1968-06-04 1969-05-23

Country Status (3)

Country Link
DE (1) DE1812347C3 (en)
GB (1) GB1251400A (en)
SE (1) SE347379B (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN110379525A (en) * 2019-08-02 2019-10-25 上海核工程研究设计院有限公司 A kind of rodlike nuclear fuel element of crash-proof and preparation method thereof
CN110415838A (en) * 2019-08-02 2019-11-05 上海核工程研究设计院有限公司 A kind of rodlike nuclear fuel element and preparation method thereof enhancing safety

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CA1327692C (en) * 1989-09-15 1994-03-15 Il Hiun Kuk Uranium silicide dispersion fuel utilizing rapid solidification by atomization and fuel fabrication process therefor
CN110993134B (en) * 2019-11-12 2023-01-06 中国工程物理研究院材料研究所 U-shaped connector 3 Si 2 Preparation method of alloy fuel

Cited By (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
CN110379525A (en) * 2019-08-02 2019-10-25 上海核工程研究设计院有限公司 A kind of rodlike nuclear fuel element of crash-proof and preparation method thereof
CN110415838A (en) * 2019-08-02 2019-11-05 上海核工程研究设计院有限公司 A kind of rodlike nuclear fuel element and preparation method thereof enhancing safety
CN110379525B (en) * 2019-08-02 2022-05-10 上海核工程研究设计院有限公司 Rod-shaped nuclear fuel element resistant to accidents and preparation method thereof
CN110415838B (en) * 2019-08-02 2022-07-22 上海核工程研究设计院有限公司 Rod-shaped nuclear fuel element with enhanced safety and preparation method thereof

Also Published As

Publication number Publication date
SE347379B (en) 1972-07-31
DE1812347B2 (en) 1974-05-22
DE1812347C3 (en) 1975-01-02
DE1812347A1 (en) 1971-06-09

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Legal Events

Date Code Title Description
PS Patent sealed [section 19, patents act 1949]
PLNP Patent lapsed through nonpayment of renewal fees