RELAP5 and TRACE codes comparison and validation under steady-state and transient conditions on the basis of NUPEC data
2007 (English)In: 12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12, 2007Conference paper (Refereed)
One-dimensional system codes are one of the main tools for the safety analysis of nuclear power plants. For BWR applications, it is of particular interest to know the performance of system codes in predicting void fraction, pressure drops, and, possibly, critical power in a wide range of conditions. The BFBT (BWR Full-Scale Fine-Mesh Bundle Tests) Benchmark , based on the NUPEC experiments, allows an accurate evaluation of the capabilities of the thermal-hydraulic codes in predicting the earlier mentioned quantities. The goal of this work is to evaluate the performance of RELAP5 and TRACE against the NUPEC experimental data. The fuel bundle employed in the benchmark has been modeled in the RELAP5 and TRACE input by a simple PIPE component using the fluid temperature and the mass flow rate as the inlet boundary condition and the pressure as the outlet boundary condition. We assessed the capability of RELAP5 and TRACE in predicting the void fraction, pressure drops and critical power in both steady-state and transient conditions. The obtained results were compared with the NUPEC measured data.
Place, publisher, year, edition, pages
IdentifiersURN: urn:nbn:se:kth:diva-55207ScopusID: 2-s2.0-44349127315ISBN: 0-89448-058-8ISBN: 978-089448058-4OAI: oai:DiVA.org:kth-55207DiVA: diva2:471055
12th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH-12. Pittsburgh, PA. 30 September 2007 - 4 October 2007
QC 201201032011-12-312011-12-312012-01-03Bibliographically approved