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Spangler, G.W.; Boling, M.; Rhoades, W.A.; Willis, C.A.
Rockwell International Corp., Canoga Park, CA (USA). Energy Systems Group1967
Rockwell International Corp., Canoga Park, CA (USA). Energy Systems Group1967
AbstractAbstract
[en] The COMRADEX Code is discussed briefly and instructions are provided for the use of the code. The subject code was developed for calculating doses from hypothetical power reactor accidents. It permits the user to analyze four successive levels of containment with time-varying leak rates. Filtration, cleanup, fallout and plateout in each containment shell can also be analyzed. The doses calculated include the direct gamma dose from the containment building, the internal doses to as many as 14 organs including the thyroid, bone, lung, etc. from inhaling the contaminated air, and the external gamma doses from the cloud. While further improvements are needed, such as a provision for calculating doses from fallout, rainout and washout, the present code capabilities have a wide range of applicability for reactor accident analysis
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1 Aug 1967; 83 p; Available from NTIS, PC A05/MF A01; 1 as DE84003693
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