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Berlad, A.L.; Sibulkin, M.; Yang, C.H.
Proceedings of the workshop on the impact of hydrogen on water reactor safety. Volume IV of IV1981
Proceedings of the workshop on the impact of hydrogen on water reactor safety. Volume IV of IV1981
AbstractAbstract
[en] Degraded core accident-related release of hydrogen under some circumstances may threaten the integrity of pressurized water reactor containment buildings. This report provides a preliminary survey of a spectrum of possible approaches which could be adopted to maintain containment building integrity under accident conditions which lead to the release of hydrogen. Particular attention is directed to large, dry containment of the Zion and Indian Point designs. For any such possible accident, there exists a sequence of time intervals characterizing the accident scenario. This report considers the generic features of these intervals and discusses the suitability of various approaches to hydrogen accident control as related to the characteristics of the interval during which they are applied. It was found that various options exist for hydrogen control strategies and that their usefulness depends on the particular accident scenarios to be considered. Of all the hydrogen control approaches considered, a strategy of continuous inerting of the containment building is the only one which clearly eliminates the combustion hazard, does not involve adverse environmental effects, and succeeds in a way that is independent of the accident scenario
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Berman, M. (ed.); Sandia National Labs., Albuquerque, NM (USA); p. 161-186; Sep 1981; p. 161-186; Workshop on the impact of hydrogen on water reactor safety; Albuquerque, NM (USA); 26-28 Jan 1981; Available from NTIS, PC A13/MF A01; 1 - GPO as DE83003257
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Report
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Conference
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