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Russcher, G.E.; Marshall, R.K.; Hesson, G.M.; Wildung, N.J.; Rausch, W.N.
Battelle Pacific Northwest Labs., Richland, WA (USA); Nuclear Regulatory Commission, Washington, DC (USA). Office of Nuclear Regulatory Research1981
Battelle Pacific Northwest Labs., Richland, WA (USA); Nuclear Regulatory Commission, Washington, DC (USA). Office of Nuclear Regulatory Research1981
AbstractAbstract
[en] A simulated loss-of-coolant accident was performed with a full-length test bundle of pressurized water reactor fuel rods. This second experiment of the program produced peak fuel cladding temperatures of 1148K (16070F) and resulted in six ruptured fuel rods. Test data and initial results from the experiment are presented here in the form of photographs and graphical summaries. These results are also compared with the preceding prototypic thermal-hydraulic test results and with computer model test predictions
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Oct 1981; 169 p; PNL--3835; Available from NTIS., PC A08/MF A01
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