GB918044A - Production of nuclear fuels, moderators or control members - Google Patents

Production of nuclear fuels, moderators or control members

Info

Publication number
GB918044A
GB918044A GB5036/59A GB503659A GB918044A GB 918044 A GB918044 A GB 918044A GB 5036/59 A GB5036/59 A GB 5036/59A GB 503659 A GB503659 A GB 503659A GB 918044 A GB918044 A GB 918044A
Authority
GB
United Kingdom
Prior art keywords
sintering
matrix
atmosphere
halogen
moderator
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
GB5036/59A
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.)
Office National dEtudes et de Recherches Aerospatiales ONERA
Original Assignee
Office National dEtudes et de Recherches Aerospatiales ONERA
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 Office National dEtudes et de Recherches Aerospatiales ONERA filed Critical Office National dEtudes et de Recherches Aerospatiales ONERA
Publication of GB918044A publication Critical patent/GB918044A/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
    • C—CHEMISTRY; METALLURGY
    • C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22C—ALLOYS
    • C22C32/00—Non-ferrous alloys containing at least 5% by weight but less than 50% by weight of oxides, carbides, borides, nitrides, silicides or other metal compounds, e.g. oxynitrides, sulfides, whether added as such or formed in situ
    • C—CHEMISTRY; METALLURGY
    • C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22C—ALLOYS
    • C22C32/00—Non-ferrous alloys containing at least 5% by weight but less than 50% by weight of oxides, carbides, borides, nitrides, silicides or other metal compounds, e.g. oxynitrides, sulfides, whether added as such or formed in situ
    • C22C32/001—Non-ferrous alloys containing at least 5% by weight but less than 50% by weight of oxides, carbides, borides, nitrides, silicides or other metal compounds, e.g. oxynitrides, sulfides, whether added as such or formed in situ with only oxides
    • C22C32/0015—Non-ferrous alloys containing at least 5% by weight but less than 50% by weight of oxides, carbides, borides, nitrides, silicides or other metal compounds, e.g. oxynitrides, sulfides, whether added as such or formed in situ with only oxides with only single oxides as main non-metallic constituents
    • C—CHEMISTRY; METALLURGY
    • C23—COATING METALLIC MATERIAL; COATING MATERIAL WITH METALLIC MATERIAL; CHEMICAL SURFACE TREATMENT; DIFFUSION TREATMENT OF METALLIC MATERIAL; COATING BY VACUUM EVAPORATION, BY SPUTTERING, BY ION IMPLANTATION OR BY CHEMICAL VAPOUR DEPOSITION, IN GENERAL; INHIBITING CORROSION OF METALLIC MATERIAL OR INCRUSTATION IN GENERAL
    • C23C—COATING METALLIC MATERIAL; COATING MATERIAL WITH METALLIC MATERIAL; SURFACE TREATMENT OF METALLIC MATERIAL BY DIFFUSION INTO THE SURFACE, BY CHEMICAL CONVERSION OR SUBSTITUTION; COATING BY VACUUM EVAPORATION, BY SPUTTERING, BY ION IMPLANTATION OR BY CHEMICAL VAPOUR DEPOSITION, IN GENERAL
    • C23C10/00—Solid state diffusion of only metal elements or silicon into metallic material surfaces
    • C23C10/06—Solid state diffusion of only metal elements or silicon into metallic material surfaces using gases
    • C23C10/08—Solid state diffusion of only metal elements or silicon into metallic material surfaces using gases only one element being diffused
    • C23C10/10—Chromising
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C21/00—Apparatus or processes specially adapted to the manufacture of reactors or parts thereof
    • G21C21/02—Manufacture of fuel elements or breeder elements contained in non-active casings
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C21/00—Apparatus or processes specially adapted to the manufacture of reactors or parts thereof
    • G21C21/02—Manufacture of fuel elements or breeder elements contained in non-active casings
    • G21C21/14—Manufacture of fuel elements or breeder elements contained in non-active casings by plating the fuel in a fluid
    • G—PHYSICS
    • G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21C—NUCLEAR REACTORS
    • G21C21/00—Apparatus or processes specially adapted to the manufacture of reactors or parts thereof
    • G21C21/18—Manufacture of control elements covered by group G21C7/00
    • 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
    • G21C7/00—Control of nuclear reaction
    • G21C7/06—Control of nuclear reaction by application of neutron-absorbing material, i.e. material with absorption cross-section very much in excess of reflection cross-section
    • G21C7/24—Selection of substances for use as neutron-absorbing 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

  • Engineering & Computer Science (AREA)
  • Physics & Mathematics (AREA)
  • Chemical & Material Sciences (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • Manufacturing & Machinery (AREA)
  • Materials Engineering (AREA)
  • Mechanical Engineering (AREA)
  • Metallurgy (AREA)
  • Organic Chemistry (AREA)
  • Chemical Kinetics & Catalysis (AREA)
  • Ceramic Engineering (AREA)
  • Dispersion Chemistry (AREA)
  • Powder Metallurgy (AREA)

Abstract

Material for use as a nuclear fuel, a moderator or a control-rod is made by mixing the corresponding nuclear fuel, moderator or absorber material, in finely-divided state, with a metallic constituent comprising one or more metals, also finely divided, the mixture being sintered in an atmosphere containing hydrogen, a halogen and a chromium halide, the surface layer formed being substantially purely metallic. The metallic constituent comprises one or more of the following: Fe, Ni, Co, Cr, Mo and alloys containing at least one of these metals. The nuclear fuel, moderator or absorber material must have a heat of formation, if a compound, high enough to prevent it being reduced by the metallic constituent during the sintering operation and form halides which are both stable and volatile under sintering conditions. The nuclear fuel may be UO2, U3O8, ThO2 or mixtures of these and may be mixed with a finely-divided moderator substance such as BeO. The absorber material may be boron. The sintering atmosphere may either be an atmosphere of hydrogen- and halogen-containing gas, e.g. a hydrogen halide which is dissociated at the temperatures employed, together with a chromium halide; or an atmosphere of hydrogen and halogen (as above) which forms chromium halide in situ, e.g. when the body to be sintered is packed in chromium fragments. The halogen in the sintering atmosphere is preferably fluorine. The metallic surface layer is plastic as well as being firmly bonded to the underlying matrix so that recompressions e.g. between two sintering stages, can be applied as on a press or in extruding and wire-drawing equipment without the risk of cracking. When U3O8 is used, a reduction to UO2 may occur under some operating conditions with the formation of Cr2O3, if chromium is present in the matrix, and this may result in a hardening of the matrix. Various oxides, e.g. Fe2O3, CeO, NgO and Al2O3 may be added to a UO2-containing mixture and during the sintering release oxygen which forms Cr2O3 in situ to harden the matrix. The mixture, prior to sintering, may be shaped and coated with a layer of Cr powder, an Fe-Cr alloy powder or a Cr-Ni alloy powder. A sheath of refractory material may be bonded to the metallic surface layer of the sintered material. Many examples of processes according to the invention are given. The Mo and Fe constituents may be present as fibres and Cd and W powders may also be added to the matrix. Uranium carbide may also be used.
GB5036/59A 1958-02-14 1959-02-13 Production of nuclear fuels, moderators or control members Expired GB918044A (en)

Applications Claiming Priority (3)

Application Number Priority Date Filing Date Title
FR758236 1958-02-14
FR763088A FR74437E (en) 1958-02-14 1958-04-14 Process for manufacturing nuclear fuel materials and products and materials and products obtained by this process
FR770850A FR75023E (en) 1958-02-14 1958-07-22 Process for manufacturing nuclear fuel materials and products, and materials and products obtained by this process

Publications (1)

Publication Number Publication Date
GB918044A true GB918044A (en) 1963-02-13

Family

ID=27245145

Family Applications (1)

Application Number Title Priority Date Filing Date
GB5036/59A Expired GB918044A (en) 1958-02-14 1959-02-13 Production of nuclear fuels, moderators or control members

Country Status (6)

Country Link
BE (1) BE575534A (en)
DE (1) DE1260153B (en)
FR (5) FR1198870A (en)
GB (1) GB918044A (en)
LU (1) LU36865A1 (en)
NL (1) NL113938C (en)

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2011101208A1 (en) 2010-02-22 2011-08-25 Westinghouse Electric Sweden Ab Nuclear fuel, nuclear fuel element, nuclear fuel assembly and a method manufacturing nuclear fuel
CN107274936A (en) * 2017-07-03 2017-10-20 中国工程物理研究院材料研究所 A kind of fast preparation method of the enhanced uranium dioxide nuclear fuel of beryllium oxide

Families Citing this family (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
BE624283A (en) * 1961-11-03
FR2817385B1 (en) * 2000-11-30 2005-10-07 Framatome Anp PASTILLE OF NUCLEAR FUEL OXIDE AND PENCIL COMPRISING A STACK OF SUCH PELLETS

Cited By (2)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
WO2011101208A1 (en) 2010-02-22 2011-08-25 Westinghouse Electric Sweden Ab Nuclear fuel, nuclear fuel element, nuclear fuel assembly and a method manufacturing nuclear fuel
CN107274936A (en) * 2017-07-03 2017-10-20 中国工程物理研究院材料研究所 A kind of fast preparation method of the enhanced uranium dioxide nuclear fuel of beryllium oxide

Also Published As

Publication number Publication date
FR1198870A (en) 1959-12-10
FR75023E (en) 1961-02-13
BE575534A (en) 1959-08-10
FR74437E (en) 1960-12-19
NL113938C (en) 1968-02-15
FR76035E (en) 1961-07-31
DE1260153B (en) 1968-02-01
FR75044E (en) 1961-02-13
LU36865A1 (en) 1959-08-11

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