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AbstractAbstract
[en] A discussion of the WRAP system and the TRAC thermal reactor safety computer code is given. Emphasis is placed on numerical methods used to solve the one- and three-dimensional fluid flow equations in TRAC and the fuel rod conduction equations during reflood. An ATWS neutronics model is also discussed
Original Title
PWR; BWR
Primary Subject
Secondary Subject
Source
May 1979; 22 p; LA--7856-MS; Available from NTIS., PC A02/MF A01
Record Type
Report
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INIS VolumeINIS Volume
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