BE570983A - - Google Patents

Info

Publication number
BE570983A
BE570983A BE570983DA BE570983A BE 570983 A BE570983 A BE 570983A BE 570983D A BE570983D A BE 570983DA BE 570983 A BE570983 A BE 570983A
Authority
BE
Belgium
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.)
Publication of BE570983A publication Critical patent/BE570983A/xx

Links

Classifications

    • C—CHEMISTRY; METALLURGY
    • C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22C—ALLOYS
    • C22C43/00—Alloys containing radioactive materials
    • C—CHEMISTRY; METALLURGY
    • C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22C—ALLOYS
    • C22C21/00—Alloys based on aluminium
    • C—CHEMISTRY; METALLURGY
    • C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22C—ALLOYS
    • C22C21/00—Alloys based on aluminium
    • C22C21/003—Alloys based on aluminium containing at least 2.6% of one or more of the elements: tin, lead, antimony, bismuth, cadmium, and titanium
    • C—CHEMISTRY; METALLURGY
    • C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
    • C22C—ALLOYS
    • C22C21/00—Alloys based on aluminium
    • C22C21/02—Alloys based on aluminium with silicon as the next major constituent
    • 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
    • G21C3/60—Metallic fuel; Intermetallic dispersions
    • 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

  • Chemical & Material Sciences (AREA)
  • Engineering & Computer Science (AREA)
  • Materials Engineering (AREA)
  • Mechanical Engineering (AREA)
  • Metallurgy (AREA)
  • Organic Chemistry (AREA)
  • Physics & Mathematics (AREA)
  • Dispersion Chemistry (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Monitoring And Testing Of Nuclear Reactors (AREA)
  • Coating With Molten Metal (AREA)
BE570983D 1957-09-10 BE570983A (pt)

Applications Claiming Priority (1)

Application Number Priority Date Filing Date Title
US683192A US2950188A (en) 1957-09-10 1957-09-10 Method of suppressing ual4 formation in u-al alloys

Publications (1)

Publication Number Publication Date
BE570983A true BE570983A (pt)

Family

ID=24742942

Family Applications (1)

Application Number Title Priority Date Filing Date
BE570983D BE570983A (pt) 1957-09-10

Country Status (5)

Country Link
US (1) US2950188A (pt)
BE (1) BE570983A (pt)
DE (1) DE1118471B (pt)
FR (1) FR1210887A (pt)
GB (1) GB893189A (pt)

Families Citing this family (9)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3147110A (en) * 1961-11-27 1964-09-01 Dow Chemical Co Die-expressed article of aluminum-base alloy and method of making
US3147111A (en) * 1961-11-27 1964-09-01 Dow Chemical Co Article of aluminum-base alloy
FR1410253A (fr) * 1964-07-01 1965-09-10 Cie Pour L Etude Et La Realisa Nouveaux alliages d'uranium pour combustibles nucléaires
DE3042424A1 (de) * 1980-11-11 1982-06-16 Kernforschungszentrum Karlsruhe Gmbh, 7500 Karlsruhe Plattenfoermiges hochleistungs-kernbrennstoff-element mit niedrig-angereichertem uran und verfahren zu seiner herstellung
US4963317A (en) * 1989-09-13 1990-10-16 The United States Of America As Represented By The United States Department Of Energy High loading uranium fuel plate
US7380321B2 (en) * 2006-03-28 2008-06-03 The Boeing Company Machining technique with selective and localized placement of tooling material
FR2909071B1 (fr) * 2006-11-23 2009-08-21 Promiles Sa Gilet de sauvetage
KR101800265B1 (ko) 2011-10-21 2017-11-22 꽁빠뉘 뿌르 레뛰드 에 라 레알리자씨옹 드 꽁뷔스띠블 아토미크 저농축 우라늄의 많은 로딩을 가지는 핵 연료 제품들을 생산하기 위한 방법 및 상응하는 핵연료 제품
EP4170681A1 (en) 2021-10-19 2023-04-26 Framatome Plate-shaped nuclear fuel element and method of manufacturing the same

Family Cites Families (4)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US2778730A (en) * 1944-09-29 1957-01-22 Frank H Spedding Plutonium alloy and method of separating it from uranium
US2743174A (en) * 1946-04-25 1956-04-24 John R Keeler Uranium-titanium alloys
US2799642A (en) * 1951-07-13 1957-07-16 Jr Henry Hurwitz Neutronic reactor fuel element
US2798848A (en) * 1951-07-13 1957-07-09 Kenneth H Kingdon Neutronic reactor fuel element

Also Published As

Publication number Publication date
DE1118471B (de) 1961-11-30
GB893189A (en) 1962-04-04
FR1210887A (fr) 1960-03-11
US2950188A (en) 1960-08-23

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