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Kim, S.H.; Kim, D.H.; Koh, B.R.; Pessanha, J.; SiAhmed, E.K.; Podowski, M.Z.; Lahey, R.T. Jr.
Oak Ridge National Lab., TN (USA); Rensselaer Polytechnic Inst., Troy, NY (USA)1988
Oak Ridge National Lab., TN (USA); Rensselaer Polytechnic Inst., Troy, NY (USA)1988
AbstractAbstract
[en] This report summarizes the thermal-hydraulic models used in APRIL. MOD2. This digital computer code was developed at Rensselaer Polytechnic Institute Corporation (ESEERCO) and the Boiling Water Reactor Severe Accident Technology Program at Oak Ridge National Laboratory (ORNL). The APRIL.MOD2 code can be used for the mechanistic analysis of severe accident phenomena in Boiling Water Nuclear Reactors (BWRs) having either Mark-I or Mark-II containment systems
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Jul 1988; 279 p; ORNL/SUB--81-9089/3; NTIS, PC A13/MF A01 - US Govt. Printing Office; 1 as TI88012914; Portions of this document are illegible in microfiche products.
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