Current Status of ACE Format Libraries for MCNP at Nuclear Data Center of KAERI

Kim, Do Heon; Gil, Choong-Sup; Lee, Young‐Ouk

doi:10.14407/jrpr.2016.41.3.191

Cited by 4 publications

(1 citation statement)

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“…All of benchmark calculations were performed using Monte Carlo Transport code MCNPX 2.7.0. The ENDF/B-VII.1-based KNE71 library [8] was used for all nuclides except for the thermal scattering cross sections of D in D 2 O and/or O in D 2 O. All the MCNP benchmark simulations were carried out at 293.6K.…”

Section: Criticality Benchmark Problemsmentioning

confidence: 99%

Validation of Thermal Neutron Scattering Cross Sections for Heavy Water based on Molecular Dynamics Simulation

2019

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Recently, the thermal scattering libraries of ENDF/B-VIII.0 and JEFF-3.3 for light and heavy water were released with a new water model (CAB model) proposed by Damian. For the CAB model, the molecular dynamics code GROMACS was used to more accurately describe the realistic motions of water molecules. In this paper, to consider the coherent component we also generated the thermal scattering cross section of the deuterium and oxygen bound in the heavy water molecules using the GROMACS code and EPSR code. In addition, the frequency spectrum was also calculated using the GROMACS code. Thermal scattering cross sections based on the newly calculated Sköld correction factor and the frequency spectrum were generated by NJOY2016 code. Finally, the performance of the generated thermal scattering cross sections were validated by performing an ICSBEP benchmark simulation using MCNPX code.

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Section: Criticality Benchmark Problemsmentioning

confidence: 99%