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AbstractAbstract
[en] A LOCA analysis of FORSMARK-I, a Swedish BWR with a new design which includes internal circulation pumps, is performed with RELAP4 for the hypothetical case of a double-ended guillotine rupture of a feedwater pipe. The code is applied once to the whole reactor system and once to a hot channel in the core. Some parametric variations are performed. The calculated maximum cladding temperature does not exceed 4000C. (author)
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1978; 8 p; ENS/ANS international topical meeting on nuclear power reactor safety; Brussels, Belgium; 16 - 19 Oct 1978; 4 refs.
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