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Samoilov, O.B.; Malamud, V.A.; Nikiporets, U.G.; Sergeev, Y.A.; Kuznetsov, U.A.
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] The experience of the development and creation of the integral AST-500 reactor for district heating with natural coolant circulation has allowed to implement the same concept for ATETS-150 PWR for small power PWR (80-240 MW(e)) with heat usage for process needs. The distinctive features of advanced reactor system and directions of their development are: primary circuit in common pressure vessel, natural coolant circulation, simplicity, passive safety systems with self-actuated controlling devices, reactor vessel enclosed in second (guard) vessel, favourable conditions for management of the most severe accident. (author)
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Source
Oka, Y.; Koshizuka, S. (Tokyo Univ. (Japan)) (comps.); Atomic Energy Society of Japan, Tokyo (Japan); [2182 p.]; 1992; v. 1 p. 6.1/1-6.1/5; 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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