Lloyd et al., 1961 - Google Patents
IMPROVEMENTS IN OR RELATING TO NUCLEAR FUEL MATERIALSLloyd et al., 1961
- Document ID
- 9679650088095679453
- Author
- Lloyd H
- Williams J
- Wheatley C
- George D
- Publication year
External Links
Snippet
A ceramic fuel material consisting of a fissile oxidedispersed in a nonfissile oxide is described which has very low permeability to fission product gases at high temperatures. The nonfissile oxide may be Al/sub 2/O/sub 3/, MgO, BeO, or ZrO/sub 2/to which an …
- 239000000463 material 0 title abstract description 14
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
- G21C3/623—Oxide fuels
-
- 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
- G21C3/04—Constructional details
- G21C3/06—Casings; Jackets
- G21C3/07—Casings; Jackets characterised by their material, e.g. alloys
-
- 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
- G21C3/04—Constructional details
- G21C3/16—Details of the construction within the casing
-
- 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 GASES [GHG] EMISSION, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
- Y02E30/38—Fuel
-
- 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 GASES [GHG] EMISSION, RELATED TO ENERGY GENERATION, TRANSMISSION OR DISTRIBUTION
- Y02E30/00—Energy generation of nuclear origin
- Y02E30/30—Nuclear fission reactors
- Y02E30/40—Other aspects relating to nuclear fission
-
- 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
- C04B35/01—Shaped ceramic products characterised by their composition; Ceramics compositions; Processing powders of inorganic compounds preparatory to the manufacturing of ceramic products based on oxide ceramics
-
- C—CHEMISTRY; METALLURGY
- C22—METALLURGY; FERROUS OR NON-FERROUS ALLOYS; TREATMENT OF ALLOYS OR NON-FERROUS METALS
- C22C—ALLOYS
- C22C16/00—Alloys based on zirconium
Similar Documents
Publication | Publication Date | Title |
---|---|---|
Chubb et al. | Properties of Uranium Carbides | |
Lloyd et al. | IMPROVEMENTS IN OR RELATING TO NUCLEAR FUEL MATERIALS | |
Street et al. | THE UC-UN AND ThC-ThN SYSTEMS | |
Howie | Radiation Damage in Ceramics | |
Samsonov et al. | Physical properties of titanium nitride in the homogeneity region | |
Maruya et al. | ACTIVATED SINTERING OF URANIUM DIOXIDE FUEL. I. SINTERING IN HYDROGEN | |
Elleman et al. | Fission-Fragment-Induced Stresses in Ceramic Materials | |
Kislii et al. | The Diffusion of Boron in Carbon | |
Yacout et al. | ALD coating of nuclear fuel actinides materials | |
Ryshkewitch | Sintered Beryllia | |
Livey | THE FABRICATION, PROPERTIES, AND IRRADIATION STABILITY OF DISPERSION-TYPE FUELS | |
Fiegel et al. | EQUILIBRIUM STUDIES OF REFRACTORY METAL OXIDES. 7 Month Report, June 13, 1961 to January 13, 1962 | |
Huddle et al. | IMPROVEMENTS IN OR RELATING TO COATING OF URANIUM METAL AND URANIUM-BASE ALLOY | |
Vasilos et al. | MICROSTRUCTURE STUDIES OF POLYCRYSTALLINE REFRACTORY OXIDES. Quarterly Progress Report No. 1, June 12 to September 12, 1962 | |
Coffinberry | PLUTONIUM-URANIUM-TITANIUM ALLOYS | |
Cunningham et al. | OXIDATION RESISTANCE OF OXIDE-COATED UO $ sub 2$ MICROSPHERES | |
Billson et al. | Manufacture of nuclear fuel porous particles | |
Schwartz | SPECIAL REPORT ON FABRICATION AND CHEMICAL REACTIVITY OF MOLYBDENUM | |
Ryshkewitch et al. | METHOD FOR PRODUCING HIGH PURITY MONOCRYSTALLINE BERYLLIA FIBERS AND PLATELETS | |
Saller et al. | The Fabrication and Compatibility of Metallic Fuel Elements for High-temperature Service | |
Prokhoshkin et al. | OXIDATION OF Nb-Zr ALLOYS | |
Whittemore Jr | PROCESS OF MAKING A NUCLEAR FUEL ELEMENT | |
Amonenko et al. | REACTION BETWEEN HEAT-RESISTING ALLOYS AND REFRACTORY OXIDES AT HIGH TEMPERATURES IN VACUUM | |
Shapiro | RESUME OF URANIUM OXIDE--II | |
Smalley et al. | INVESTIGATION OF SINTERABLE POWDERS AND BERYLLIUM OXIDE PROPERTIES. Quarterly Report No. 1 for February 15, 1959 through April 30, 1959 |