Benchmarking the new ENDF/B-VIII.0 nuclear data library for the first core of Indonesian multipurpose research reactor (RSG GAS)
In: EPJ Web of Conferences, Jg. 239 (2020), S. 22007-22007
Online
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Zugriff:
The Indonesian Multipurpose Research Reactor namely Reaktor Serba Guna G.A. Siwabessy (RSG GAS) is a 30 MWth (max.) pool-type reactor loaded with plate-type low-enriched uranium fuel, using light water as coolant and moderator, and beryllium as reflector. The benchmark of the 1st criticality core of RSG GAS using different nuclear data libraries such as JENDL-4.0, JENDL-3.3, ENDF/B-VII.0, and JEFF-3.1 have been performed in the previous work and compared with the experiment result. In this work, the newly released ENDF/B-VIII.0 neutron reaction and thermal neutron scattering libraries will be used and the important neu-tronics parameters such as multiplication factor, kinetics parameters, and fission reaction rate will be calculated using Monte Carlo code MCNP6.2 and compared against the previous work and the experiment result.
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Benchmarking the new ENDF/B-VIII.0 nuclear data library for the first core of Indonesian multipurpose research reactor (RSG GAS)
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Autor/in / Beteiligte Person: | Donny, Hartanto ; Victor, Gillette ; Sembiring Tagor Malem ; Liem Peng Hong |
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Zeitschrift: | EPJ Web of Conferences, Jg. 239 (2020), S. 22007-22007 |
Veröffentlichung: | EDP Sciences, 2020 |
Medientyp: | academicJournal |
ISSN: | 2100-014X (print) |
DOI: | 10.1051/epjconf/202023922007 |
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