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Long, J.K.; Marchese, A.R.; Speis, T.P.; Gasser, R.D.; Pratt, W.T.
International meeting on fast reactor safety technology1979
International meeting on fast reactor safety technology1979
AbstractAbstract
[en] A radiological and containment evaluation was made for a number of core meltdown sequences for a sodium cooled reactor (FFTF). These sequences include in-vessel retention and ex-vessel release of core debris, the behavior of coolable and noncoolable debris beds, failure and survival of cavity liners, and behavior of radioactive aerosols of sodium products. The analyses show that the buildup of pressure and hydrogen in containment is critically dependent on sodium-concrete reactions following a possible liner failure. 9 refs
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Source
Anon; p. 1251-1260; 1979; p. 1251-1260; American Nuclear Society; LaGrange Park, IL; International meeting on fast reactor safety technology; Seattle, WA, USA; 19 - 23 Aug 1979
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Book
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Conference
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