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Anand, A.K.; Anantharaman, K.; Basu, S.; Mehta, S.K.
Specialists' meeting on pellet-cladding interaction in water reactors, Risoe National Laboratory, Denmark, 22-26 September 19801981
Specialists' meeting on pellet-cladding interaction in water reactors, Risoe National Laboratory, Denmark, 22-26 September 19801981
AbstractAbstract
[en] Performance of the COMTA computer program developed for predicting pellet-clad interactions was experimentally evaluated on well characterized fuel rods in pressurized water loop, located in the CIRUS research reactor at Bhabha Atomic Research Centre. Experimental data obtained in 5x1013 n/cm2 neutron flux post-irradiation examination of UO2, UO2-PuO2 pellets and zircaloy tubing was used for comparison
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International Atomic Energy Agency, Vienna (Austria). International Working Group on Fuel Performance and Technology for Water Reactors; p. 31-33; Jan 1981; p. 31-33; Specialists' meeting on pellet-cladding interaction in water reactors; Roskilde, Denmark; 22 - 26 Sep 1980
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Report
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Conference
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ACTINIDE COMPOUNDS, ALLOYS, CHALCOGENIDES, COMPUTER CODES, ENERGY SOURCES, FUELS, NUCLEAR FUELS, OXIDES, OXYGEN COMPOUNDS, PLUTONIUM COMPOUNDS, PLUTONIUM OXIDES, RADIATION EFFECTS, REACTOR COMPONENTS, REACTOR MATERIALS, SOLID FUELS, TIN ALLOYS, TRANSITION ELEMENT ALLOYS, TRANSURANIUM COMPOUNDS, URANIUM COMPOUNDS, URANIUM OXIDES, ZIRCONIUM ALLOYS, ZIRCONIUM BASE ALLOYS
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