Code-to-code comparison between TINTE and MGT for steady state scenario
Autor: | Claudia Druska, S. Kasselmann, Hans-Josef Allelein, K. Nünighoff |
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Rok vydání: | 2012 |
Předmět: |
Nuclear and High Energy Physics
Engineering Neutron transport Temperature control business.industry Mechanical Engineering Nuclear engineering Control rod Nuclear reactor Neutron temperature law.invention Thermal hydraulics Nuclear Energy and Engineering Nuclear reactor core law Benchmark (computing) General Materials Science Safety Risk Reliability and Quality business Waste Management and Disposal Simulation |
Zdroj: | Nuclear Engineering and Design. 251:111-116 |
ISSN: | 0029-5493 |
Popis: | Based on the scenarios defined in the OECD-NEA benchmark “PBMR Coupled Neutronics/Thermal Hydraulics Transient Benchmark of the PBMR-400 Core Design”, a code-to-code comparison was performed between the reactor dynamics program TINTE (Time Dependent Neutronics and Temperatures) using two neutron energy groups and the advanced code MGT (Multi Group TINTE) which is able to take into account up to 43 energy groups. The effect of an increasing number of energy groups on time- and space dependent safety-related parameters like the fuel and moderator temperature, the reactivity or the control rod worth has been studied. In a first step, calculations were carried out to compare the results obtained from MGT and TINTE using two energy groups. Afterwards the MGT two-group model was compared to a scenario using 43 energy groups. In addition, the benchmark was well suited to validate the new nuclear library of MGT now based on ENDF/B-VII.0 data. |
Databáze: | OpenAIRE |
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