GB1107300A - Moderator-nuclear fuel element - Google Patents

Moderator-nuclear fuel element

Info

Publication number
GB1107300A
GB1107300A GB15117/66A GB1511766A GB1107300A GB 1107300 A GB1107300 A GB 1107300A GB 15117/66 A GB15117/66 A GB 15117/66A GB 1511766 A GB1511766 A GB 1511766A GB 1107300 A GB1107300 A GB 1107300A
Authority
GB
United Kingdom
Prior art keywords
yttrium
fuel
nuclear fuel
molybdenum
april
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
GB15117/66A
Inventor
Andre Bourrasse
Yvette Carteret
Jean Elston
Renee Lucas
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 GB1107300A publication Critical patent/GB1107300A/en
Expired legal-status Critical Current

Links

Classifications

    • 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
    • G21C3/16—Details of the construction within the casing
    • G21C3/20—Details 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
    • 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
    • G21C3/42—Selection of substances for use as reactor fuel
    • G21C3/58—Solid reactor fuel Pellets made of fissile material
    • 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)
  • Silicon Compounds (AREA)
  • Fuel Cell (AREA)

Abstract

1,107,300. Nuclear fuel elements. COMMISSARIAT A L'ENERGIE ATOMIQUE. 5 April, 1966 [26 April, 1965], No. 15117/66. Heading G6C. A nuclear fuel element comprises refractory nuclear fuel particles dispersed in yttrium hydride as moderator, the fuel particles being coated with a material which does not react with yttrium hydride. The fuel element may be enclosed in a can of molybdenum or refractory alloy lined with a nitride, carbide, silicide, boride, or oxide layer, or with an aluminium silicate-zirconium silicate enamel to inhibit diffusion of hydrogen. A molybdenum layer may be interposed between the fuel and the can. The element may be made by mixing ground yttrium with spherical U0 2 particles coated with molybdenum, pressing hydraulically, sintering at 1000-1200‹ C., placing in a metal can, and then hydriding the yttrium; a heat insulating MgO pellet may be inserted and then an end cap fixed. The element is suitable for use at high temperatures in a space vehicle propulsion nuclear reactor employing alkali metal as coolant.
GB15117/66A 1965-04-26 1966-04-05 Moderator-nuclear fuel element Expired GB1107300A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR14664A FR1441629A (en) 1965-04-26 1965-04-26 moderator-fuel element

Publications (1)

Publication Number Publication Date
GB1107300A true GB1107300A (en) 1968-03-27

Family

ID=8577304

Family Applications (1)

Application Number Title Priority Date Filing Date
GB15117/66A Expired GB1107300A (en) 1965-04-26 1966-04-05 Moderator-nuclear fuel element

Country Status (6)

Country Link
US (1) US3342692A (en)
BE (1) BE679037A (en)
CH (1) CH455069A (en)
FR (1) FR1441629A (en)
GB (1) GB1107300A (en)
LU (1) LU50956A1 (en)

Families Citing this family (12)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3994778A (en) * 1971-07-15 1976-11-30 The United States Of America As Represented By The United States Energy Research And Development Administration Liquid metal hydrogen barriers
JPS534199B2 (en) * 1974-05-22 1978-02-15
US4029545A (en) * 1974-11-11 1977-06-14 General Electric Company Nuclear fuel elements having a composite cladding
US4022662A (en) * 1974-11-11 1977-05-10 General Electric Company Nuclear fuel element having a metal liner and a diffusion barrier
US4032400A (en) * 1976-02-17 1977-06-28 The United States Of America As Represented By The United States Energy Research And Development Administration Nuclear reactor fuel element with vanadium getter on cladding
JPS59184885A (en) * 1983-04-06 1984-10-20 株式会社日立製作所 Fuel assembly
US4751041A (en) * 1986-01-15 1988-06-14 Westinghouse Electric Corp. Burnable neutron absorber element
US6233299B1 (en) * 1998-10-02 2001-05-15 Japan Nuclear Cycle Development Institute Assembly for transmutation of a long-lived radioactive material
CN111276265B (en) * 2019-12-31 2022-05-20 中国核动力研究设计院 Rod type fuel element using uranium-yttrium hydride fuel
US11443858B2 (en) * 2020-07-10 2022-09-13 Uchicago Argonne, Llc Neutron moderation modules
CN113969361B (en) * 2021-10-27 2023-05-16 中国核动力研究设计院 Preparation method of high-purity yttrium, preparation method of yttrium hydride pellet and yttrium hydride pellet
CN114804028B (en) * 2022-05-09 2024-04-30 西安稀有金属材料研究院有限公司 Crack-free yttrium hydride neutron moderating material for space reactor and preparation method thereof

Family Cites Families (6)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3096263A (en) * 1952-04-01 1963-07-02 Walter E Kingston Nuclear reactor fuel elements and method of preparation
US3170847A (en) * 1959-12-15 1965-02-23 Joseph A Dudek Self-moderating fuel element
US3088892A (en) * 1960-05-05 1963-05-07 Jr Francis M Cain Dispersion element consisting of chromium coated uo2 particles uniformly distributedin a zircaloy matrix
US3167655A (en) * 1960-08-30 1965-01-26 Redstone Reuben Target for a neutron generator consisting of a coating of one of the lanthanon elements on a base metal
NL275685A (en) * 1961-03-16
US3154845A (en) * 1962-02-08 1964-11-03 Gen Dynamics Corp Method of fabricating a fuel element

Also Published As

Publication number Publication date
CH455069A (en) 1968-04-30
US3342692A (en) 1967-09-19
LU50956A1 (en) 1966-06-27
BE679037A (en) 1966-09-16
FR1441629A (en) 1966-06-10

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