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AbstractAbstract
[en] The FRAP-T6 code was developed at the Idaho National Engineering Laboratory (INEL) for the purpose of calculating the transient performance of light water reactor fuel rods during reactor transients ranging from mild operational transients to severe hypothetical loss-of-coolant accidents. An important application of the FRAP-T6 code is to calculate the structural performance of fuel rod cladding. The capabilities of the FRAP-T6 code are assessed by comparisons of code calculations with the measurements of several hundred in-pile experiments on fuel rods. The results of the assessments show that the code accurately and efficiently models the structural and thermal response of fuel rods
Original Title
PWR; BWR
Primary Subject
Secondary Subject
Source
1983; 12 p; 7. international conference on structural mechanics in reactor technology; Chicago, IL (USA); 22-26 Aug 1983; CONF-830805--57; Available from NTIS, PC A02/MF A01; 1 as DE84000836
Record Type
Report
Literature Type
Conference
Report Number
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Reference NumberReference Number
INIS VolumeINIS Volume
INIS IssueINIS Issue