GB1411024A - Method of fabricating porous cermets containing a fissile material - Google Patents

Method of fabricating porous cermets containing a fissile material

Info

Publication number
GB1411024A
GB1411024A GB2550173A GB2550173A GB1411024A GB 1411024 A GB1411024 A GB 1411024A GB 2550173 A GB2550173 A GB 2550173A GB 2550173 A GB2550173 A GB 2550173A GB 1411024 A GB1411024 A GB 1411024A
Authority
GB
United Kingdom
Prior art keywords
powder
paraffin
granules
cermet
coating
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
GB2550173A
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 GB1411024A publication Critical patent/GB1411024A/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
    • G21C3/42—Selection of substances for use as reactor fuel
    • G21C3/58—Solid reactor fuel Pellets made of fissile material
    • G21C3/62—Ceramic fuel
    • G21C3/64—Ceramic dispersion fuel, e.g. cermet
    • 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

Abstract

1411024 Nuclear fuel COMMISSARIAT A L'ENERGIE ATOMIQUE 29 May 1973 [5 June 1972] 25501/73 Heading G6C A porous cermet for use as nuclear fuel is made by coating granules of a fissile material, such as uranium oxide or plutonium oxide, successively with a pore-producing substance and a metal powder, and sintering the product. In one embodiment, a UO 2 -Mo cermet is made by coating UO 2 granules with MoO 3 powder mixed with a solution of paraffin in ether, and then with Mo powder; the paraffin is removed and the granules compacted into pellets, sintered at 1600‹ C. in hydrogen, and annealed at 2000‹ C. The paraffin may be replaced by stearic acid or acrylic resin. In another process, a UO 2 -W cermet is made by coating chips of compacted UO 2 powder with a solution of stearic acid or ammonium behenate in ether, drying, mixing with W powder, compacting, and sintering. Other metals referred to are Fe, Ni, Nb, and stainless steel. Other processes are described in which the coated particles are sintered without compacting into pellets and are enclosed in a can to form a fuel element. Oxides of W, Fe, Ni, or Nb may be used in place of MoO 3 . Reference is also made to using carbide or nitride fuel particles in place of oxide particles.
GB2550173A 1972-06-05 1973-05-29 Method of fabricating porous cermets containing a fissile material Expired GB1411024A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR7220052A FR2187724B1 (en) 1972-06-05 1972-06-05

Publications (1)

Publication Number Publication Date
GB1411024A true GB1411024A (en) 1975-10-22

Family

ID=9099663

Family Applications (1)

Application Number Title Priority Date Filing Date
GB2550173A Expired GB1411024A (en) 1972-06-05 1973-05-29 Method of fabricating porous cermets containing a fissile material

Country Status (2)

Country Link
FR (1) FR2187724B1 (en)
GB (1) GB1411024A (en)

Cited By (5)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2954849A1 (en) * 2009-12-31 2011-07-01 Commissariat Energie Atomique PROCESS FOR PRODUCING A CERMET COMPRISING URANIUM DIOXIDE PARTICLES
FR2954850A1 (en) * 2009-12-31 2011-07-01 Commissariat Energie Atomique IMPROVED THERMAL CONDUCTIVITY CERMET AND NUCLEAR COMBUSTIBLE COMPRISING THE CERMET
CN110828001A (en) * 2019-10-23 2020-02-21 中国工程物理研究院材料研究所 Heat conductivity improved uranium dioxide-based fuel pellet for improving uranium loading and preparation method thereof
CN111326265A (en) * 2020-02-28 2020-06-23 中国工程物理研究院材料研究所 Uranium dioxide-carbide composite fuel pellet and preparation method thereof
CN112820431A (en) * 2020-12-31 2021-05-18 中核北方核燃料元件有限公司 Metal wall microcapsule nuclear fuel pellet added with oxide and preparation method thereof

Cited By (9)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
FR2954849A1 (en) * 2009-12-31 2011-07-01 Commissariat Energie Atomique PROCESS FOR PRODUCING A CERMET COMPRISING URANIUM DIOXIDE PARTICLES
FR2954850A1 (en) * 2009-12-31 2011-07-01 Commissariat Energie Atomique IMPROVED THERMAL CONDUCTIVITY CERMET AND NUCLEAR COMBUSTIBLE COMPRISING THE CERMET
WO2011080474A1 (en) * 2009-12-31 2011-07-07 Commissariat A L'energie Atomique Et Aux Energies Alternatives Method for producing a cermet comprising uranium dioxide particles
WO2011080475A1 (en) * 2009-12-31 2011-07-07 Commissariat A L'energie Atomique Et Aux Energies Alternatives Cermet with improved heat conductivity and nuclear fuel comprising said cermet
CN110828001A (en) * 2019-10-23 2020-02-21 中国工程物理研究院材料研究所 Heat conductivity improved uranium dioxide-based fuel pellet for improving uranium loading and preparation method thereof
CN110828001B (en) * 2019-10-23 2021-09-28 中国工程物理研究院材料研究所 Heat conductivity improved uranium dioxide-based fuel pellet for improving uranium loading and preparation method thereof
CN111326265A (en) * 2020-02-28 2020-06-23 中国工程物理研究院材料研究所 Uranium dioxide-carbide composite fuel pellet and preparation method thereof
CN111326265B (en) * 2020-02-28 2023-05-02 中国工程物理研究院材料研究所 Uranium dioxide-carbide composite fuel pellet and preparation method thereof
CN112820431A (en) * 2020-12-31 2021-05-18 中核北方核燃料元件有限公司 Metal wall microcapsule nuclear fuel pellet added with oxide and preparation method thereof

Also Published As

Publication number Publication date
DE2327872B2 (en) 1976-10-28
FR2187724A1 (en) 1974-01-18
DE2327872A1 (en) 1973-12-20
FR2187724B1 (en) 1980-04-18

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Legal Events

Date Code Title Description
PS Patent sealed
PCNP Patent ceased through non-payment of renewal fee