GB1031678A - Improvements in or relating to cermets - Google Patents
Improvements in or relating to cermetsInfo
- 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
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
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.
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)
| 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 |
-
1962
- 1962-11-30 GB GB45291/62A patent/GB1031678A/en not_active Expired
-
1963
- 1963-11-29 BE BE640634D patent/BE640634A/xx unknown
Cited By (18)
| 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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