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Jahn, H.L.; Langer, G.
Proceedings of the workshop on the impact of hydrogen water reactor safety. Volume III of IV1981
Proceedings of the workshop on the impact of hydrogen water reactor safety. Volume III of IV1981
AbstractAbstract
[en] The computer code RALOC has been applied to several old and new PWR plants to determine the hydrogen distribution after a loss-of-coolant accident (design basis accident (DBA)) with and without function of special mixing and recombining hydrogen control systems. Some development has been done to include those control systems and other features but some code modification and verification still remains. Especially the simulation of structural heat influences is considered to demand advanced simulation. This is a matter of present code development. This situation also has meaning for studies of more severe accidents than DBA. It is definitely intended to derive a RALOC version to study situations such as core melt accidents
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Berman, M. (ed.); Sandia National Labs., Albuquerque, NM (USA); p. 271-278; Sep 1981; p. 271-278; Workshop on the impact of hydrogen on water reactor safety; Albuquerque, NM (USA); 26-28 Jan 1981; Available from NTIS, PC A15/MF A01; 1 - GPO as DE83003258
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Conference
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