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2. COBRA-IV, 1976. An interim version of COBRA for thermal–hydraulic analysis of rod bundle nuclear fuel elements and cores, BNWL-1962.
3. Convective Boiling and Condensation;Collier,1980
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5. Dynamic calculations of the IAEA safety MTR research reactor benchmark problem using RELAP5/3.2 code;Hamidouche;Annals of Nuclear Energy,2004