Influence of Modelling Options in RELAP5/SCDAPSIM and MAAP4 Computer Codes on Core Melt Progression and Reactor Pressure Vessel Integrity
Author(s) -
Siniša Šadek,
Srđan Špalj,
Bruno Glaser
Publication year - 2009
Publication title -
science and technology of nuclear installations
Language(s) - English
Resource type - Journals
SCImago Journal Rank - 0.417
H-Index - 24
eISSN - 1687-6083
pISSN - 1687-6075
DOI - 10.1155/2010/163279
Subject(s) - blackout , nuclear engineering , reactor pressure vessel , thermal hydraulics , leakage (economics) , coolant , transient (computer programming) , core (optical fiber) , engineering , nuclear reactor core , environmental science , reliability engineering , mechanical engineering , computer science , mechanics , heat transfer , thermodynamics , power (physics) , telecommunications , physics , macroeconomics , operating system , economics , electric power system
RELAP5/SCDAPSIM and MAAP4 are two widely used severe accident computer codes for the integral analysis of the core and the reactor pressure vessel behaviour following the core degradation. The objective of the paper is the comparison of code results obtained by application of different modelling options and the evaluation of influence of thermal hydraulic behaviour of the plant on core damage progression. The analysed transient was postulated station blackout in NPP Krško with a leakage from reactor coolant pump seals. Two groups of calculations were performed where each group had a different break area and, thus, a different leakage rate. Analyses have shown that MAAP4 results were more sensitive to varying thermal hydraulic conditions in the primary system. User-defined parameters had to be carefully selected when the MAAP4 model was developed, in contrast to the RELAP5/SCDAPSIM model where those parameters did not have any significant impact on final results
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