Analysis of the peach bottom 2 BWR turbine trip experiment by RELAP 5/3.2 code
Autor: | Francesko D'auria, Anis Bousbia-Salah |
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Jazyk: | angličtina |
Rok vydání: | 2002 |
Předmět: |
Neutron transport
business.industry Nuclear engineering Experimental data Nuclear power Turbine Relap5 system code Nuclear Energy and Engineering sensitivity analysis BWR turbine trip Environmental science Boiling water reactor lcsh:QC770-798 lcsh:Nuclear and particle physics. Atomic energy. Radioactivity Reference case Steam line Safety Risk Reliability and Quality business Sensitivity analyses experimental results |
Zdroj: | Nuclear Technology and Radiation Protection, Vol 17, Iss 1-2, Pp 44-49 (2002) |
ISSN: | 1451-3994 |
Popis: | This paper presents the results of the application of the system of the thermalhydraulic code RELAP5/Mod3.2 in predicting the Peach Bottom Boiling Water Reactor Turbine Trip test. This experiment constitutes a challenge to the capabilities of current computational tools in realistically predicting transient scenarios in nuclear power plants. In fact, it involves strong feedback during the transient between thermalhydraulics and neutronics. In this respect, a reference case was run in order to simulate the interactions between the generated steam line pressure wave propagation and the instantaneous core void distribution. An overall comparison shows good agreement between the code calculations and the experimental data. A series of sensitivity analyses were also performed in order to assess the code prediction features, as well as to identify uncertainties related to the adopted thermalhydraulic parameters used for the plant modelisation. |
Databáze: | OpenAIRE |
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