Home / Publications / Journals / Nuclear Technology / Volume 90 / Number 3
Nuclear Technology / Volume 90 / Number 3 / June 1990 / Pages 340-355
Technical Paper / RELAP/MOD2 / Heat Transfer and Fluid Flow / dx.doi.org/10.13182/NT90-A34399
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Assessment of the RELAP5/MOD2 code on the basis of experiments performed in a pressurized water reactor simulator, the LOBI/MOD2 facility at the European Research Center of Ispra in Italy is reported. In particular, significant experience gained in the analysis of two small-break loss-of-coolant accidents (tests A2-81 and A1-83), a steam generator tube rupture (test BL-21), a natural circulation (test A2-77A), and four transients (tests A2-90, BT-00, BT-01, and BT-03) is discussed.