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Showing 1 to 4 of 4 for “"Serpent 2"”.
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Neutronics and thermal-hydraulics analysis of transatomic power molten salt reactor (TAP MSR) core under load following operations
… operations using a Monte Carlo code, Serpent 2, as well as a UIUC-developed MOOSE-based code, Moltres. A simulation method was developed to determine the operational bounds of the TAP MSR core and its transient behavior under rapid power ramps using both fresh fuel salt and fuel salt …
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Advancement and verification of Moltres for molten salt reactor safety analysis
… Monte Carlo neutron transport results from Serpent 2. The multiplication factors k_eff, delayed neutron fractions beta, temperature reactivity coefficient alpha_T, and the six-group neutron energy spectra from Moltres agreed with the high fidelity simulation results from Serpent 2. The k_eff …
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Advanced online fuel reprocessing simulation for thorium-fueled molten salt breeder reactor
… SaltProc couples with the Monte Carlo code, SERPENT 2, for neutron transport and depletion calculations. SaltProc capabilities include a generic geometry capable of modeling multi-region and multi-flow systems, time-dependent feeds and removals, and specific separation efficiency for each …
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Impact of nuclear data libraries for criticality calculation of HTGR
… Test Reactor (HTTR) and HTR-10 reactor models. Serpent 2 was used to calculate criticality and its uncertainty due to nuclear data, using data from evaluated nuclear data libraries ENDF/B-VIII.1 and JENDL-5. Uncertainty quantification demonstrates that for both HTTR and HTR-10, keff uncertainty …