Kirihara, Tomoo; Yamawaki, Michio; Obata, Naomi; Handa, Muneo.
Kyoto Univ., Kumatori, Osaka (Japan). Research Reactor Inst1983
Kyoto Univ., Kumatori, Osaka (Japan). Research Reactor Inst1983
AbstractAbstract
[en] It was attempted to take up the behavior of nuclear fuel in cores and summarize it by the expert committee on the irradiation behavior of nuclear fuel from fiscal 1978 to fiscal 1980 from the following viewpoints. The behavior of nuclear fuel in cores has been treated separately according to each reactor type, accordingly this point is reconsidered. The clearly understood points and the uncertain points are discriminated. It is made more easily understandable for people in other fields of atomic energy. This report is that of the group on the chemical interaction, and the first report of this committee. The chemical interaction as the behavior of fuel in cores is in the unseparable relation to the mechanical interaction, but this relation is not included in this report. The chemical interaction of fuel and cladding tubes under irradiation shows different phenomena in LWRs and FBRs, and is called SCC and FCC, respectively. But this point of causing the difference must be understood to grasp the behavior of fuel. The mutual comparison of oxide fuels for FBRs and LWRs, the stress corrosion cracking of zircaloy tubes, and fuel-cladding chemical interaction in FBRs are reported. (Kako, I.)
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1983; 65 p
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Report
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ALLOY-ZR98SN-2, ALLOY-ZR98SN-4, BWR TYPE REACTORS, CHEMICAL REACTION KINETICS, CHROMIUM-NICKEL-MOLYBDENUM STE, COMPARATIVE EVALUATIONS, CRACK PROPAGATION, CRACKS, FISSION PRODUCTS, FUEL CANS, FUEL RODS, FUEL-CLADDING INTERACTIONS, INTERGRANULAR CORROSION, LMFBR TYPE REACTORS, MIXED OXIDE FUELS, OXYGEN POTENTIAL, PWR TYPE REACTORS, STEEL-CR17NI12MO3, STRESS CORROSION, URANIUM DIOXIDE
ACTINIDE COMPOUNDS, ALLOYS, AUSTENITIC STEELS, BREEDER REACTORS, CARBON ADDITIONS, CHALCOGENIDES, CHEMICAL REACTIONS, CHROMIUM ADDITIONS, CHROMIUM ALLOYS, CHROMIUM-NICKEL STEELS, CORROSION, CORROSION RESISTANT ALLOYS, ENERGY, ENERGY SOURCES, ENRICHED URANIUM REACTORS, EPITHERMAL REACTORS, FAST REACTORS, FBR TYPE REACTORS, FREE ENTHALPY, FUEL ELEMENTS, FUELS, HEAT RESISTING ALLOYS, HIGH ALLOY STEELS, IRON ADDITIONS, IRON ALLOYS, IRON BASE ALLOYS, ISOTOPES, KINETICS, LIQUID METAL COOLED REACTORS, MATERIALS, MOLYBDENUM ALLOYS, NICKEL ADDITIONS, NICKEL ALLOYS, NUCLEAR FUELS, OXIDES, OXYGEN COMPOUNDS, PHYSICAL PROPERTIES, POWER REACTORS, RADIOACTIVE MATERIALS, REACTION KINETICS, REACTOR COMPONENTS, REACTOR MATERIALS, REACTORS, SOLID FUELS, STAINLESS STEELS, STEELS, THERMAL REACTORS, THERMODYNAMIC PROPERTIES, TIN ALLOYS, URANIUM COMPOUNDS, URANIUM OXIDES, WATER COOLED REACTORS, WATER MODERATED REACTORS, ZIRCALOY, ZIRCONIUM ALLOYS, ZIRCONIUM BASE ALLOYS
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AbstractAbstract
No abstract available
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Record Type
Journal Article
Journal
Nippon Kinzoku Gakkai-Shi; v. 37(1); p. 100-103
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AbstractAbstract
[en] In order to obtain the optimum conditions for micro-hardness measurements of sintered UO2, two kinds of hardness tests (Vickers and Knoop) were examined with non-irradiated UO2 of 2.5 and 5 μm in grain size. The hardness values were obtained as a function of the applied load in the load range of 25 -- 1,000 g. In the Vickers test, cracks were generated around the periphery of an indentation even at lower load of 50 g, which means the Vickers hardness is not suitable for UO2 specimens. In the Knoop test, three stages of load dependence were observed for sintered pellet as well as for a single crystal by Bates. Load dependence of Knoop hardness and crack formation were discussed. In the range of applied load around 70 -- 100 g there were plateau region where hardness values were nearly unchanged and did not contain any cracks in the indentation. The plateau region represents a hardness of a specimen. From a comparison between the hardness values of 2.5 μm and those of 5 μm UO2, it was approved that the degree of sintering controls the hardness in the plateau region. (author)
Primary Subject
Record Type
Journal Article
Journal
Nippon Genshiryoku Gakkai-Shi; ISSN 0004-7120;
; v. 25(2); p. 140-147

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