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AbstractAbstract
[en] The analysis of the FR-2 in-pile Loss of Coolant Accident was carried out using FRAP-T6 code. The clad temperature was introduced as that of the coolant with a very high heat transfer coefficient. The clad temperature, the fuel temperature at the center of the rod, the internal pressure variation, stress and strain distribution and the rupture time were calculated and compared to the measured values. Sensitivity studies were carried out and were found to improve the agreement between the calculated and the experimental results. (author). 15 refs, 11 figs, 3 tabs
Primary Subject
Source
International Atomic Energy Agency, Vienna (Austria); 259 p; Jun 1993; p. 44-52; Technical committee meeting on behaviour of core materials and fission product release in accident conditions in LWRs; Aix-en-Provence (France); 16-19 Mar 1992
Record Type
Report
Literature Type
Conference; Numerical Data
Report Number
Country of publication
ACCIDENTS, COMPUTER CODES, DATA, FAILURES, FUEL ELEMENTS, HEAVY WATER COOLED REACTORS, HEAVY WATER MODERATED REACTORS, INFORMATION, IRRADIATION REACTORS, ISOTOPE PRODUCTION REACTORS, NATURAL URANIUM REACTORS, NUMERICAL DATA, REACTOR ACCIDENTS, REACTOR COMPONENTS, REACTORS, RESEARCH AND TEST REACTORS, RESEARCH REACTORS, TANK TYPE REACTORS, TEST FACILITIES, TEST REACTORS, THERMAL REACTORS
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