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AbstractAbstract
[en] Fuel behavior studies in simulated reactivity initiated accident (RIA) conditions have been performed by utilizing Nuclear Safety Research Reactor (NSRR) since October, 1975. This report describes the results obtained from January through December, 1984. A total of 62 tests were carried out during this period; those are 6 fuel design parameter tests (2 long-sized fuel rod tests, 4 pre-irradiated clad fuel rod tests), 3 cooling condition parameter tests (2 forced convection tests and 1 bundle rod test), 4 defected fuel rod tests (4 fretting corroded clad fuel rod tests), 3 severe fuel damage tests, 18 special fuel rod tests (2 HTGR fuel tests, 5 mixed oxide fuel rod tests, 11 Gd2O3-UO2 fuel rod tests), 18 miscellaneous atomspheric pressure capsule tests (mechanical energy measurement tests, fuel rod deformation measurement tests, etc), 4 high temperature high pressure capsule tests, 2 high temperature high pressure loop tests and 4 fuel behavior observation tests. (author)
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Source
Feb 1986; 191 p
Record Type
Report
Literature Type
Progress Report
Report Number
Country of publication
ACCIDENTS, CHEMICAL REACTIONS, COMPUTER CODES, CONVECTION, CORROSION, ENERGY TRANSFER, ENRICHED URANIUM REACTORS, FUEL ELEMENTS, HEAT TRANSFER, HOMOGENEOUS REACTORS, HYDRIDE MODERATED REACTORS, JAPANESE ORGANIZATIONS, MIXED SPECTRUM REACTORS, NATIONAL ORGANIZATIONS, PULSED REACTORS, RADIATION EFFECTS, REACTOR ACCIDENTS, REACTOR COMPONENTS, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, SOLID HOMOGENEOUS REACTORS, WATER COOLED REACTORS, WATER MODERATED REACTORS
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