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Shinaishin, M.A.; Talha, K.A.; Abdou, H.N.; Arafa, H.; Helal, M.M.
ANP'92 international conference on design and safety of advanced nuclear power plants1992
ANP'92 international conference on design and safety of advanced nuclear power plants1992
AbstractAbstract
[en] A Computer Code has been developed with the objective of: (1) Simulating the primary and secondary circuits and the control system for a typical Pressurized Water Reactor - Nuclear Power Plant PWR - NPP ; (2) Simulating the reactor protection and scram system; (3) PWR-Dry Containment atmosphere and sump modeling; and (4) Analysis of the Nuclear Steam Supply System (NSSS) and of the containment response to selected accidents. The results indicate that in it's present status the code is capable of simple and fast simulation of plant conditions up to and including DBAs. It remains, however, to develop it for severe accident simulation and to have the NSSS models linked to the containment simulation models. (author)
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Oka, Y.; Koshizuka, S. (Tokyo Univ. (Japan)) (comps.); Atomic Energy Society of Japan, Tokyo (Japan); [2182 p.]; 1992; v. 4 p. P17.3/1-P17.3/15; Atomic Energy Society of Japan; Tokyo (Japan); ANP'92: international conference on design and safety of advanced nuclear power plants; Tokyo (Japan); 25-29 Oct 1992
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Book
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Conference
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