Results of the codes simulating transients and abnormal conditions in nuclear power plants are inevitably uncertain. In application to thermal-hydraulic calculations by thermal-hydraulics codes, uncertainty importance analysis can be used to quantitatively confirm the results of qualitative phenomena identification and ranking table (PIRT). Several methodologies have been developed to address u...

As a part of the TEPSS project, within the last fourth Framework Programme of the European Union R&D activities, an investigation focused on the residual heat removal passive safety systems in the future boiling water reactors was performed using PANDA facility and the codes RELAP5, MELCOR and TRAC-BF l. The main purpose was to ensure the capacity of these passive safety systems under a wide ra...

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It is known, that the phenomena of phase change and boiling crisis are not yet fully deciphered, which leads to generation technical problems, such as frequent breakdowns accidental shutdowns in thermal installations. The main objective this study numerical analysis an ascending flow during a vertical channel by Relap5/Mod3.2 code. This code can helps heat transfer convection, boiling, condensa...