GB1411024A - Method of fabricating porous cermets containing a fissile material - Google Patents
Method of fabricating porous cermets containing a fissile materialInfo
- Publication number
- GB1411024A GB1411024A GB2550173A GB2550173A GB1411024A GB 1411024 A GB1411024 A GB 1411024A GB 2550173 A GB2550173 A GB 2550173A GB 2550173 A GB2550173 A GB 2550173A GB 1411024 A GB1411024 A GB 1411024A
- Authority
- GB
- United Kingdom
- Prior art keywords
- powder
- paraffin
- granules
- cermet
- coating
- 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)
- Powder Metallurgy (AREA)
- Inorganic Compounds Of Heavy Metals (AREA)
Abstract
1411024 Nuclear fuel COMMISSARIAT A L'ENERGIE ATOMIQUE 29 May 1973 [5 June 1972] 25501/73 Heading G6C A porous cermet for use as nuclear fuel is made by coating granules of a fissile material, such as uranium oxide or plutonium oxide, successively with a pore-producing substance and a metal powder, and sintering the product. In one embodiment, a UO 2 -Mo cermet is made by coating UO 2 granules with MoO 3 powder mixed with a solution of paraffin in ether, and then with Mo powder; the paraffin is removed and the granules compacted into pellets, sintered at 1600‹ C. in hydrogen, and annealed at 2000‹ C. The paraffin may be replaced by stearic acid or acrylic resin. In another process, a UO 2 -W cermet is made by coating chips of compacted UO 2 powder with a solution of stearic acid or ammonium behenate in ether, drying, mixing with W powder, compacting, and sintering. Other metals referred to are Fe, Ni, Nb, and stainless steel. Other processes are described in which the coated particles are sintered without compacting into pellets and are enclosed in a can to form a fuel element. Oxides of W, Fe, Ni, or Nb may be used in place of MoO 3 . Reference is also made to using carbide or nitride fuel particles in place of oxide particles.
Applications Claiming Priority (1)
Application Number | Priority Date | Filing Date | Title |
---|---|---|---|
FR7220052A FR2187724B1 (en) | 1972-06-05 | 1972-06-05 |
Publications (1)
Publication Number | Publication Date |
---|---|
GB1411024A true GB1411024A (en) | 1975-10-22 |
Family
ID=9099663
Family Applications (1)
Application Number | Title | Priority Date | Filing Date |
---|---|---|---|
GB2550173A Expired GB1411024A (en) | 1972-06-05 | 1973-05-29 | Method of fabricating porous cermets containing a fissile material |
Country Status (2)
Country | Link |
---|---|
FR (1) | FR2187724B1 (en) |
GB (1) | GB1411024A (en) |
Cited By (5)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR2954849A1 (en) * | 2009-12-31 | 2011-07-01 | Commissariat Energie Atomique | PROCESS FOR PRODUCING A CERMET COMPRISING URANIUM DIOXIDE PARTICLES |
FR2954850A1 (en) * | 2009-12-31 | 2011-07-01 | Commissariat Energie Atomique | IMPROVED THERMAL CONDUCTIVITY CERMET AND NUCLEAR COMBUSTIBLE COMPRISING THE CERMET |
CN110828001A (en) * | 2019-10-23 | 2020-02-21 | 中国工程物理研究院材料研究所 | Heat conductivity improved uranium dioxide-based fuel pellet for improving uranium loading and preparation method thereof |
CN111326265A (en) * | 2020-02-28 | 2020-06-23 | 中国工程物理研究院材料研究所 | Uranium dioxide-carbide composite fuel pellet and preparation method thereof |
CN112820431A (en) * | 2020-12-31 | 2021-05-18 | 中核北方核燃料元件有限公司 | Metal wall microcapsule nuclear fuel pellet added with oxide and preparation method thereof |
-
1972
- 1972-06-05 FR FR7220052A patent/FR2187724B1/fr not_active Expired
-
1973
- 1973-05-29 GB GB2550173A patent/GB1411024A/en not_active Expired
Cited By (9)
Publication number | Priority date | Publication date | Assignee | Title |
---|---|---|---|---|
FR2954849A1 (en) * | 2009-12-31 | 2011-07-01 | Commissariat Energie Atomique | PROCESS FOR PRODUCING A CERMET COMPRISING URANIUM DIOXIDE PARTICLES |
FR2954850A1 (en) * | 2009-12-31 | 2011-07-01 | Commissariat Energie Atomique | IMPROVED THERMAL CONDUCTIVITY CERMET AND NUCLEAR COMBUSTIBLE COMPRISING THE CERMET |
WO2011080475A1 (en) * | 2009-12-31 | 2011-07-07 | Commissariat A L'energie Atomique Et Aux Energies Alternatives | Cermet with improved heat conductivity and nuclear fuel comprising said cermet |
WO2011080474A1 (en) * | 2009-12-31 | 2011-07-07 | Commissariat A L'energie Atomique Et Aux Energies Alternatives | Method for producing a cermet comprising uranium dioxide particles |
CN110828001A (en) * | 2019-10-23 | 2020-02-21 | 中国工程物理研究院材料研究所 | Heat conductivity improved uranium dioxide-based fuel pellet for improving uranium loading and preparation method thereof |
CN110828001B (en) * | 2019-10-23 | 2021-09-28 | 中国工程物理研究院材料研究所 | Heat conductivity improved uranium dioxide-based fuel pellet for improving uranium loading and preparation method thereof |
CN111326265A (en) * | 2020-02-28 | 2020-06-23 | 中国工程物理研究院材料研究所 | Uranium dioxide-carbide composite fuel pellet and preparation method thereof |
CN111326265B (en) * | 2020-02-28 | 2023-05-02 | 中国工程物理研究院材料研究所 | Uranium dioxide-carbide composite fuel pellet and preparation method thereof |
CN112820431A (en) * | 2020-12-31 | 2021-05-18 | 中核北方核燃料元件有限公司 | Metal wall microcapsule nuclear fuel pellet added with oxide and preparation method thereof |
Also Published As
Publication number | Publication date |
---|---|
FR2187724A1 (en) | 1974-01-18 |
FR2187724B1 (en) | 1980-04-18 |
DE2327872A1 (en) | 1973-12-20 |
DE2327872B2 (en) | 1976-10-28 |
Similar Documents
Publication | Publication Date | Title |
---|---|---|
US3504058A (en) | Process for manufacturing sintered pellets of nuclear fuel | |
GB930655A (en) | Improvements relating to boiling moderator reactors | |
GB1507878A (en) | Mixed oxide nuclear fuel | |
GB1411024A (en) | Method of fabricating porous cermets containing a fissile material | |
Chalder et al. | The fabrication and properties of uranium dioxide fuel | |
GB1034505A (en) | Improvements in or relating to sintered uranium-plutonium compounds | |
US3114689A (en) | Ceramic fuel for nuclear reactors | |
GB1128742A (en) | Nuclear fuel element and method of fabricating of said element | |
GB1115452A (en) | Nuclear fuel elements | |
GB1370928A (en) | Fuel and/or fertile material for nuclear reactors | |
US3761546A (en) | Method of making uranium dioxide bodies | |
GB1334391A (en) | Nuclear fuels | |
GB1371595A (en) | Manufacturing process for mixed nuclear fuel pellets | |
Bel et al. | SINTERING OF URANIUM OXIDE IN HYDROGEN AT 1350 C | |
GB1437691A (en) | Method of mahuffacturing cermets from isotopic sources and products obtained thereby | |
GB928517A (en) | Improvements in and relating to fuel elements for nuclear reactors | |
GB1404520A (en) | ||
GB1182080A (en) | Nuclear Fuel | |
GB1305308A (en) | ||
GB1281977A (en) | Method of producing composite bodies from loose heaps of metal-coated particles of fuel and/or fertile material for nuclear reactors | |
GB1303052A (en) | ||
Ferris | Miscellaneous Experiments Relating to the Processing of CETR Fuel by Sulfex-Thorex and Darex-Thorex Processes | |
GB1468261A (en) | Nuclear fuel particles for use in the manufacture of nuclear fuel bodies | |
US3291697A (en) | Fuel element for nuclear reactor | |
Rasmussen et al. | Alternative oxide fuel pellet fabrication for irradiation testing.[LMFBR] |
Legal Events
Date | Code | Title | Description |
---|---|---|---|
PS | Patent sealed | ||
PCNP | Patent ceased through non-payment of renewal fee |