Sheinhartz, 1959 - Google Patents
NON-OXIDE DISPERSION TYPE FUEL ELEMENTSSheinhartz, 1959
- Document ID
- 11096458694025351215
- Author
- Sheinhartz I
- Publication year
- Publication venue
- Nuclear Sci. and Eng.
External Links
Snippet
A series of dispersant type alloys was investigated to determine the feasibility of using the alloys as fuel elements. The dispersants investigated were UNs U/sub 3/Si/sub 2/, UC, and US. The matrix materials investigated were Al, Zircaloy-2, Mo, Nb, Nichrome V, Ti-Nb alloyss …
- 239000000446 fuel 0 title abstract description 32
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
- G21C3/02—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
- G21C3/42—Selection of substances for use as reactor fuel
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C19/00—Arrangements for treating, for handling, or for facilitating the handling of, fuel or other materials which are used within the reactor, e.g. within its pressure vessel
- G21C19/42—Reprocessing of irradiated fuel
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C17/00—Monitoring; Testing ; Maintaining
- G21C17/02—Devices or arrangements for monitoring coolant or moderator
- G21C17/022—Devices or arrangements for monitoring coolant or moderator for monitoring liquid coolants or moderators
-
- G—PHYSICS
- G21—NUCLEAR PHYSICS; NUCLEAR ENGINEERING
- G21C—NUCLEAR REACTORS
- G21C21/00—Apparatus or processes specially adapted to the manufacture of reactors or parts thereof
- G21C21/02—Manufacture of fuel elements or breeder elements contained in non-active casings
- G21C21/10—Manufacture of fuel elements or breeder elements contained in non-active casings by extrusion, drawing, or stretching by rolling, e.g. "picture frame" technique
-
- 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
-
- 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
- Y02E30/34—Fast breeder reactors
Similar Documents
Publication | Publication Date | Title |
---|---|---|
Hughes et al. | The effects of neutron irradiation at elevated temperatures on the tensile properties of some austenitic stainless steels | |
Boettcher et al. | Some properties of uranium monocarbide | |
Paprocki et al. | Preparation of Reactor Components by a Gas-Pressure Bonding Technique | |
Klopp | Oxidation behavior and protective coatings for columbium and columbium-base alloys | |
Sheinhartz | NON-OXIDE DISPERSION TYPE FUEL ELEMENTS | |
Christensen | HIGH-TEMPERATURE, SHORT-TIME, URANIUM CARBIDE-METAL REACTIONS | |
Macherey et al. | Materials for Argonne National Laboratory sodium cooled reactors | |
Richter et al. | SOME INVESTIGATIONS ON CERAMICS AND CERMET MATERIALS FOR THE PRODUCTION OF BLADES FOR CUTTING TOOLS | |
Shober et al. | Investigation of the yield phenomenon in Zircaloy-2 at elevated temperatures | |
Shapiro et al. | Uranium Dioxide Fuel Materials with Improved Thermal Conductivity | |
Cowan | MINUTES OF URANIUM OXIDE PANEL MEETING | |
Fisher | MATERIALS FOR NUCLEAR POWERPLANTS | |
Myers | Summary of Third HEF Combustion Product Corrosion Working Group Meeting | |
Green et al. | Dispersion Strengthening of Molybdenum at High Temperatures | |
Megeff et al. | INVESTIGATIONS ON STAINLESS STEEL-UO $ sub 2$ FUEL ELEMENT CORE MATERIAL | |
Paprocki et al. | INCORPORATION OF A BORON BURNABLE POISON AND SPHERICAL UO $ sub 2$ IN SM-2 STAINLESS-MATRIX FUEL PLATES | |
Ida et al. | NUCLEAR FUEL ELEMENTS | |
Dimpel | POSSIBILITIES FOR THE APPLICATION OF NONFERROUS METALS IN REACTOR TECHNOLOGY | |
Friske et al. | Effect of Low Alloy Additions on the Properties of Uranium | |
Britton et al. | THE RESISTANCE OF ZIRCONIUM AND ITS ALLOYS TO HIGH TEMPERATURE WATER | |
Minor | IRRADIATION EFFECTS IN CLADDING MATERIALS | |
Richt et al. | METALLOGRAPHIC EXAMINATION OF IRRADIATED CERAMIC FUEL ELEMENTS AND CERMET SHIELDING MATERIALS. Report No. 1 | |
McIntosh et al. | Plutonium fuel and nuclear power | |
Dayton et al. | Progress Report for August 1955 | |
Bruch et al. | METALLURGY REPORT OF THE RESEARCH OPERATION FOR JUNE, JULY, AUGUST 1956 |