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GB1031678A - Improvements in or relating to cermets - Google Patents

Improvements in or relating to cermets

Info

Publication number
GB1031678A
GB1031678A GB45291/62A GB4529162A GB1031678A GB 1031678 A GB1031678 A GB 1031678A GB 45291/62 A GB45291/62 A GB 45291/62A GB 4529162 A GB4529162 A GB 4529162A GB 1031678 A GB1031678 A GB 1031678A
Authority
GB
United Kingdom
Prior art keywords
particles
strips
stainless steel
coated
die
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
GB45291/62A
Inventor
John Henry Gittus
Lewis Rhoslyn Williams
George Arthur Baily
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.)
UK Atomic Energy Authority
Original Assignee
UK Atomic Energy Authority
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 UK Atomic Energy Authority filed Critical UK Atomic Energy Authority
Priority to GB45291/62A priority Critical patent/GB1031678A/en
Priority to BE640634D priority patent/BE640634A/xx
Publication of GB1031678A publication Critical patent/GB1031678A/en
Expired legal-status Critical Current

Links

Classifications

    • GPHYSICS
    • G21NUCLEAR PHYSICS; NUCLEAR ENGINEERING
    • G21CNUCLEAR REACTORS
    • G21C3/00Reactor fuel elements and their assemblies; Selection of substances for use as reactor fuel elements
    • G21C3/42Selection of substances for use as reactor fuel
    • G21C3/58Solid reactor fuel Pellets made of fissile material
    • G21C3/62Ceramic fuel
    • G21C3/64Ceramic dispersion fuel, e.g. cermet
    • YGENERAL 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
    • Y02TECHNOLOGIES OR APPLICATIONS FOR MITIGATION OR ADAPTATION AGAINST CLIMATE CHANGE
    • Y02EREDUCTION OF GREENHOUSE GAS [GHG] EMISSIONS, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
    • Y02E30/00Energy generation of nuclear origin
    • Y02E30/30Nuclear fission reactors

Landscapes

  • Engineering & Computer Science (AREA)
  • Chemical & Material Sciences (AREA)
  • Ceramic Engineering (AREA)
  • Physics & Mathematics (AREA)
  • Dispersion Chemistry (AREA)
  • Plasma & Fusion (AREA)
  • General Engineering & Computer Science (AREA)
  • High Energy & Nuclear Physics (AREA)
  • Other Surface Treatments For Metallic Materials (AREA)

Abstract

<PICT:1031678/C6-C7/1> <PICT:1031678/C6-C7/2> A cermet having particles of ceramic material dispersed in a continuous metal matrix is made by placing in a die alternate layers of ceramic particles, one particle in depth, and layers of metal matrix material and subsequently pressing the contents of the die to form a compact which is then sintered at an elevated temperature. In one embodiment (Fig. 2), a nuclear fuel cermet is made by rolling VO2 particles 1 in an adhesive such as resin and then in stainless steel powder so as to produce a coating 3 of the latter, alternate layers of the coated particles and thin stainless steel sheets 4 being placed in a die 5 and pressed to form a compact which is sintered at 1000 DEG C., and then hot rolled at 1000 DEG to 1200 DEG C. Each of the layers of coated particles may be covered by a layer of stainless steel powder after being placed in the die and before being covered by the next stainless steel strip in the assembly. Alternatively (Fig. 7), UO2 particles 1 are dropped on to strips 3, of a combustible material such as cellulose or of stainless steel, coated with a layer 4 of adhesive such as sulphur-free rubber solution, the particle coated strips 3 being placed in a die 5 alternately with layers of stainless steel powder 6. The contents of the die 5 are cold compacted under pressure to form a compact which is sintered at 1000 DEG C. and then hot rolled at 1000 DEG to 1200 DEG C. The hot rolling is carried out in directions parallel to the layers of particles, e.g. in the direction of the arrow Y and at right angles to this direction and in the same plane, to draw the particles apart which in the finished product are separated by stainless steel. In order to obtain a desired degree of separation and a desired patter of distribution of the particles, each strip 3 may (Fig. 4, not shown) be coated with discrete spots 7 of adhesive so that when loose particles 1 are dropped on to such a strip, one particle 1 will adhere to each spot 7. In alternative methods of coating the strips 3 with ceramic fissile particles the strips 3 are coated with particles 1 in parallel lines either by first coating the strips with parallel lines 8 of adhesive (Fig. 5, not shown) and then shaking particles 1 on to the strips, or by transversely corrugating adhesive coated strips 3 (Fig. 6, not shown), shaking particles 1 on to the strips, and subsequently removing the corrugations by applying longitudinal tension or by rolling the strips. The compacts formed from such strips are hot rolled only in a direction parallel to the lines of particles. In any of the above methods, the particles may be coated with stainless steel powder and these particles may be dropped through a plasma flame to fuse the powder coatings into solid metal coatings.
GB45291/62A 1962-11-30 1962-11-30 Improvements in or relating to cermets Expired GB1031678A (en)

Priority Applications (2)

Application Number Priority Date Filing Date Title
GB45291/62A GB1031678A (en) 1962-11-30 1962-11-30 Improvements in or relating to cermets
BE640634D BE640634A (en) 1962-11-30 1963-11-29

Applications Claiming Priority (2)

Application Number Priority Date Filing Date Title
GB45291/62A GB1031678A (en) 1962-11-30 1962-11-30 Improvements in or relating to cermets
GB169163 1963-01-14

Publications (1)

Publication Number Publication Date
GB1031678A true GB1031678A (en) 1966-06-02

Family

ID=30445227

Family Applications (1)

Application Number Title Priority Date Filing Date
GB45291/62A Expired GB1031678A (en) 1962-11-30 1962-11-30 Improvements in or relating to cermets

Country Status (2)

Country Link
BE (1) BE640634A (en)
GB (1) GB1031678A (en)

Cited By (10)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3419387A (en) * 1967-07-24 1968-12-31 Atomic Energy Commission Usa Process of making high loaded uo2-columbium cermets
US3429699A (en) * 1967-07-24 1969-02-25 Atomic Energy Commission High loaded uo2-columbium cermets
RU2124767C1 (en) * 1997-08-26 1999-01-10 Государственный научный центр РФ Всероссийский научно-исследовательский институт неорганических материалов им.акад. А.А.Бочвара Nuclear reactor fuel element
WO2011143293A1 (en) * 2010-05-11 2011-11-17 Thorium Power, Inc. Fuel assembly
US8654917B2 (en) 2007-12-26 2014-02-18 Thorium Power, Inc. Nuclear reactor (alternatives), fuel assembly of seed-blanket subassemblies for nuclear reactor (alternatives), and fuel element for fuel assembly
US9355747B2 (en) 2008-12-25 2016-05-31 Thorium Power, Inc. Light-water reactor fuel assembly (alternatives), a light-water reactor, and a fuel element of fuel assembly
US10170207B2 (en) 2013-05-10 2019-01-01 Thorium Power, Inc. Fuel assembly
US10192644B2 (en) 2010-05-11 2019-01-29 Lightbridge Corporation Fuel assembly
CN116417165A (en) * 2021-12-31 2023-07-11 中核北方核燃料元件有限公司 Manufacturing method of dispersion fuel pellet
CN116417166A (en) * 2021-12-31 2023-07-11 中核北方核燃料元件有限公司 Manufacturing method of dispersion fuel pellet

Cited By (18)

* Cited by examiner, † Cited by third party
Publication number Priority date Publication date Assignee Title
US3429699A (en) * 1967-07-24 1969-02-25 Atomic Energy Commission High loaded uo2-columbium cermets
US3419387A (en) * 1967-07-24 1968-12-31 Atomic Energy Commission Usa Process of making high loaded uo2-columbium cermets
RU2124767C1 (en) * 1997-08-26 1999-01-10 Государственный научный центр РФ Всероссийский научно-исследовательский институт неорганических материалов им.акад. А.А.Бочвара Nuclear reactor fuel element
US8654917B2 (en) 2007-12-26 2014-02-18 Thorium Power, Inc. Nuclear reactor (alternatives), fuel assembly of seed-blanket subassemblies for nuclear reactor (alternatives), and fuel element for fuel assembly
US9355747B2 (en) 2008-12-25 2016-05-31 Thorium Power, Inc. Light-water reactor fuel assembly (alternatives), a light-water reactor, and a fuel element of fuel assembly
US10037823B2 (en) 2010-05-11 2018-07-31 Thorium Power, Inc. Fuel assembly
EA023017B1 (en) * 2010-05-11 2016-04-29 Ториум Пауэр, Инк. Fuel assembly
EP3038112A1 (en) * 2010-05-11 2016-06-29 Thorium Power, Inc. Fuel assembly
WO2011143293A1 (en) * 2010-05-11 2011-11-17 Thorium Power, Inc. Fuel assembly
US10192644B2 (en) 2010-05-11 2019-01-29 Lightbridge Corporation Fuel assembly
US10991473B2 (en) 2010-05-11 2021-04-27 Thorium Power, Inc. Method of manufacturing a nuclear fuel assembly
US11195629B2 (en) 2010-05-11 2021-12-07 Thorium Power, Inc. Fuel assembly
US11837371B2 (en) 2010-05-11 2023-12-05 Thorium Power, Inc. Method of manufacturing a nuclear fuel assembly
US11862353B2 (en) 2010-05-11 2024-01-02 Thorium Power, Inc. Fuel assembly
US10170207B2 (en) 2013-05-10 2019-01-01 Thorium Power, Inc. Fuel assembly
US11211174B2 (en) 2013-05-10 2021-12-28 Thorium Power, Inc. Fuel assembly
CN116417165A (en) * 2021-12-31 2023-07-11 中核北方核燃料元件有限公司 Manufacturing method of dispersion fuel pellet
CN116417166A (en) * 2021-12-31 2023-07-11 中核北方核燃料元件有限公司 Manufacturing method of dispersion fuel pellet

Also Published As

Publication number Publication date
BE640634A (en) 1964-05-29

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