Presentation Information

11:35 AM - 11:50 AM JST(2:35 AM - 2:50 AM UTC)

[2C08]Evaluation of impact of O-in-UO2 Thermal Scattering Law (TSL) on BWR depletion calculations with MCNP6.3

*Shinichi Namizono¹, Michitaka Ono¹, Masayuki Tojo¹ (1. GNF-J)

Keywords:

Boiling Water Reactor,Depletion analysis,O-in-UO2 Thermal Scattering Law,MCNP

We prepared scattering cross sections using the O-in-UO2 Thermal Scatter Law (TSL) data in JENDL-5 with the nuclear data processing code FRENDY. We used MCNP6.3 to analyze the NEA/NSC "Burn-up Credit Criticality Safety Benchmark Phase III-C". Compared to the case where O-in-UO2 TSL cross sections are not used, we found a maximum difference of the multiplication factor of 0.25% and for the Gd-isotopes a difference in number density of 8%.

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