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Appelhans, A.D.; Dagbjartsson, S.J.
Idaho National Engineering Lab., Idaho Falls (USA); Fichtner, Beratende Ingenieure fuer Energie- und Waermewirtschaft G.m.b.H. und Co. K.G., Stuttgart (Germany, F.R.)1981
Idaho National Engineering Lab., Idaho Falls (USA); Fichtner, Beratende Ingenieure fuer Energie- und Waermewirtschaft G.m.b.H. und Co. K.G., Stuttgart (Germany, F.R.)1981
AbstractAbstract
[en] Cracking and relocation of light water reactor (LWR) fuel pellets affect the axial gas flow path within nuclear reactor fuel rods and the thermal performance of the fuel. As part of the Nuclear Regulatory Commission's Water Reactor Safety Research Fuel Behavior Program, the Thermal Fuels Behavior Program of EG and G Idaho, Inc., is conducting fuel rod behavior studies in the Heavy Boiling Water Reactor in Halden, Norway. The Instrumental Fuel Assembly-430 (IFA-430) operated in that facility is a multipurpose assembly designed to provide information on fuel cracking and relocation, the long-term thermal response of LWR fuel rods subjected to various internal pressures and gas compositions, and the release of fission gases. This report presents the results of an analysis of fuel cracking and relocation phenomena as deduced from fuel rod axial gas flow and fuel temperature data from the first 6.5 GWd/tUO2 burnup of the IFA-430
Original Title
PWR;BWR
Primary Subject
Secondary Subject
Source
1981; 14 p; 6. international conference on structural mechanics in reactor technology; Paris, France; 17 - 21 Aug 1981; Available from NTIS., PC A02/MF A01 as DE82005950
Record Type
Report
Literature Type
Conference
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