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Mitchell, R.C.; Jacob, M.C.
Proceedings of the fourth international topical meeting on nuclear thermal hydraulics, operations and safety. Vol. 12004
Proceedings of the fourth international topical meeting on nuclear thermal hydraulics, operations and safety. Vol. 12004
AbstractAbstract
[en] This paper identifies the many preventative and mitigative features of the System 80+TM Advanced Light Water Reactor (ALWR) design that reduce the probability of radiological release to the atmosphere following hypothetical Steam Generator Tube Rupture (SGTR) events. This paper discusses studies performed to evaluate the response of the plant to SGTR events. The studies include a review of nine design changes which could potentially reduce the probability of SGTR containment bypass. The results show that the current System 80+TM design incorporates significant features which (1) reduce the risk of incurring a SGTR event, (2) significantly improve event diagnosis and mitigation, and (3) accommodate hypothetical multiple tube ruptures using automatic means. Thus, reliance on speedy manual corrective measures by the plant operators is significantly reduced. (author)
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Nuclear Energy Society, Taipei, Taiwan (China); American Nuclear Society (United States); American Society of Mechanical Engineers (United States); Atomic Energy Society of Japan (Japan); Canadian Nuclear Society (Canada); Korean Nuclear Society (Korea, Republic of); 772 p; 2004; p. 25D1-25D8; 4. international topical meeting on nuclear thermal hydraulics, operations and safety; Taipei, Taiwan (China); 5-8 Apr 1994; 11 figs
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