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GB1064224A - Method of preparation of nuclear fuel material and products thus obtained - Google Patents

Method of preparation of nuclear fuel material and products thus obtained

Info

Publication number
GB1064224A
GB1064224A GB44229/64A GB4422964A GB1064224A GB 1064224 A GB1064224 A GB 1064224A GB 44229/64 A GB44229/64 A GB 44229/64A GB 4422964 A GB4422964 A GB 4422964A GB 1064224 A GB1064224 A GB 1064224A
Authority
GB
United Kingdom
Prior art keywords
range
pressure
pellets
pun
bars
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
GB44229/64A
Inventor
Francois Anselin
Roger Pascard
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 GB1064224A publication Critical patent/GB1064224A/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
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01B—NON-METALLIC ELEMENTS; COMPOUNDS THEREOF; METALLOIDS OR COMPOUNDS THEREOF NOT COVERED BY SUBCLASS C01C
    • C01B32/00—Carbon; Compounds thereof
    • C01B32/90—Carbides
    • C01B32/914—Carbides of single elements
    • C01B32/928—Carbides of actinides
    • C—CHEMISTRY; METALLURGY
    • C04—CEMENTS; CONCRETE; ARTIFICIAL STONE; CERAMICS; REFRACTORIES
    • C04B—LIME, MAGNESIA; SLAG; CEMENTS; COMPOSITIONS THEREOF, e.g. MORTARS, CONCRETE OR LIKE BUILDING MATERIALS; ARTIFICIAL STONE; CERAMICS; REFRACTORIES; TREATMENT OF NATURAL STONE
    • C04B35/00—Shaped ceramic products characterised by their composition; Ceramics compositions; Processing powders of inorganic compounds preparatory to the manufacturing of ceramic products
    • C04B35/51—Shaped ceramic products characterised by their composition; Ceramics compositions; Processing powders of inorganic compounds preparatory to the manufacturing of ceramic products based on compounds of actinides
    • 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
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01P—INDEXING SCHEME RELATING TO STRUCTURAL AND PHYSICAL ASPECTS OF SOLID INORGANIC COMPOUNDS
    • C01P2006/00—Physical properties of inorganic compounds
    • C01P2006/10—Solid density
    • C—CHEMISTRY; METALLURGY
    • C01—INORGANIC CHEMISTRY
    • C01P—INDEXING SCHEME RELATING TO STRUCTURAL AND PHYSICAL ASPECTS OF SOLID INORGANIC COMPOUNDS
    • C01P2006/00—Physical properties of inorganic compounds
    • C01P2006/80—Compositional purity
    • 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
    • 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
    • Y10—TECHNICAL SUBJECTS COVERED BY FORMER USPC
    • Y10S—TECHNICAL SUBJECTS COVERED BY FORMER USPC CROSS-REFERENCE ART COLLECTIONS [XRACs] AND DIGESTS
    • Y10S376/00—Induced nuclear reactions: processes, systems, and elements
    • Y10S376/90—Particular material or material shapes for fission reactors
    • Y10S376/901—Fuel

Landscapes

  • Engineering & Computer Science (AREA)
  • Chemical & Material Sciences (AREA)
  • Physics & Mathematics (AREA)
  • Ceramic Engineering (AREA)
  • Plasma & Fusion (AREA)
  • Organic Chemistry (AREA)
  • High Energy & Nuclear Physics (AREA)
  • General Engineering & Computer Science (AREA)
  • Inorganic Chemistry (AREA)
  • Manufacturing & Machinery (AREA)
  • Materials Engineering (AREA)
  • Structural Engineering (AREA)
  • Inorganic Compounds Of Heavy Metals (AREA)
  • Powder Metallurgy (AREA)

Abstract

1,064,224. Fuel materials. COMMISSARIAT A L'ENERGIE ATOMIQUE. Oct. 29, 1964 [Nov. 5, 1963], No. 44229/64. Heading G6C. Nuclear fuel material, for use especially in breeder reactors, consisting of a mixture of UC and PuN is prepared by mixing PuN with C -and UH 3 in suitable respective proportions, heating the mixture to form UC and sintering the resulting mixture of UC and PuN under a pressure in the range of 2,000 to 15,000 bars at a temperature in the range of 1200‹ to 1700‹ C. The preparation of the fuel may be carried out in a single operation, after the incorporation of 1% by wt. of naphthalene as binder and 0À5% by wt. of nickel as sintering adjuvant, at a temperature within the range of 1200‹ to 1700‹ C., at a pressure in the range of 2,000 to 10,000 bars and for between 2 and 6 hours. Alternatively, the ingredients in powder form are compacted to form pellets under a pressure in the range of 2,000 to 10,000 bars, which pellets are homogenized by heating in vacuo at a temperature in the range 1200‹ to 1500‹ C. for between 2 and 6 hours and then ground, the resulting powder having added to it 1% by wt. of naphthalene and 0À5% by wt. of nickel and then being compacted to form pellets under a pressure in the range of 8,000 to 15,000 bars, which pellets are sintered by heating at a temperature in the range of 1200‹ to 1500‹ C. under a pressure in the range of 10<SP>-5</SP> to 10<SP>-6</SP> mm .of Hg for between 2 and 6 hours. The sintered pellets may be subjected to an annealing treatment by heating at 1600‹ C. for between 2 and 6 hours. Fuel materials made by the first of the above methods have a density of 11À8 to 12À2 gm/cc. and those made by the second method a density of 12À4 and 13À0 gm/cc. In the fabrication of breeder reactor fuel elements, the weight percentage of PuN is advantageously within the range 2 to 25%.
GB44229/64A 1963-11-05 1964-10-29 Method of preparation of nuclear fuel material and products thus obtained Expired GB1064224A (en)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
FR952657A FR1382249A (en) 1963-11-05 1963-11-05 Process for preparing fuel elements and products obtained by this process

Publications (1)

Publication Number Publication Date
GB1064224A true GB1064224A (en) 1967-04-05

Family

ID=8815795

Family Applications (1)

Application Number Title Priority Date Filing Date
GB44229/64A Expired GB1064224A (en) 1963-11-05 1964-10-29 Method of preparation of nuclear fuel material and products thus obtained

Country Status (14)

Country Link
US (1) US3309322A (en)
AT (1) AT260373B (en)
BE (1) BE655111A (en)
CH (1) CH427060A (en)
DE (1) DE1282537B (en)
DK (1) DK114055B (en)
ES (1) ES305658A1 (en)
FR (1) FR1382249A (en)
GB (1) GB1064224A (en)
IL (1) IL22351A (en)
LU (1) LU47241A1 (en)
NL (1) NL147563B (en)
OA (1) OA00470A (en)
SE (1) SE312611B (en)

Families Citing this family (3)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3362914A (en) * 1967-06-13 1968-01-09 Atomic Energy Commission Usa Uranium carbide-plutonium phosphide as a reactor fuel
US3806565A (en) * 1971-08-02 1974-04-23 North American Rockwell Method of preparing relatively low density oxide fuel for a nuclear reactor
CN113012836A (en) * 2019-12-20 2021-06-22 中核北方核燃料元件有限公司 Preparation method of UN pellet for light water reactor

Family Cites Families (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3044946A (en) * 1961-03-17 1962-07-17 Felix B Litton High density nuclear fuel composition
NL279974A (en) * 1961-06-21
BE624283A (en) * 1961-11-03
NL294166A (en) * 1962-06-20

Also Published As

Publication number Publication date
NL6412798A (en) 1965-05-06
DK114055B (en) 1969-05-27
NL147563B (en) 1975-10-15
DE1282537B (en) 1969-03-13
AT260373B (en) 1968-03-11
CH427060A (en) 1966-12-31
ES305658A1 (en) 1966-03-16
US3309322A (en) 1967-03-14
IL22351A (en) 1968-03-28
BE655111A (en) 1965-02-15
SE312611B (en) 1969-07-21
OA00470A (en) 1966-07-15
FR1382249A (en) 1964-12-18
LU47241A1 (en) 1964-12-29

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