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Murata, K.K.; Louie, D.L.Y.
Sandia National Labs., Albuquerque, NM (USA)1988
Sandia National Labs., Albuquerque, NM (USA)1988
AbstractAbstract
[en] A parametric study of the containment response of the Grand Gulf plant, a Mark III BWR, has been conducted using the Contain code. The response to extensive debris dispersal following reactor pressure vessel failure at high pressure is examined for a short period after vessel failure, for plant conditions corresponding to a short-term station blackout scenario with water on the floor of the drywell. The discussion of results from this study focuses on the peak drywell-wetwell pressure difference, the peak pedestal pressure, and the potential for drywell flooding after debris dispersal
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1988; 20 p; 4. workshop on integrity of containments for nuclear power plants; Washington, DC (USA); 15-17 Jun 1988; CONF-880616--3; Available from NTIS, PC A03/MF A01; 1 as DE88012334; Portions are illegible in microfiche products.
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