[1J16-20] Uncertainty Analysis

[1J19] Random Sampling-Based Uncertainty Quantification using a Continuous Energy Monte Carlo Method for a Thermal Neutron System

*Hiroya Oike¹, Ryoichi Kondo¹, Tomohiro Endo¹, Akio Yamamoto¹ (1. Nagoya Univ.)

Keywords:Uncertainty Quantification, Random Sampling, Evaluated Nuclear Data Library, MCNP, Thermal Neutron System

By using the continuous energy Monte Carlo code, MCNP and the random sampling(RS) method, uncertainty quantification of the thermal neutron system Heu-sol-therm012 in the ICSBEP handbook is conducted. For RS, the random sampling code of ACE-format cross section developed by the modules of the FRENDY was used. In perturbation for RS, all reactions which 56 energy-group cross section covariance of nuclear data of SCALE 6.2.3(56groupcov7.1) contents are considered. By comparison of this result and the deterministic method one based on the first order perturbation theory(TSUNAMI-1D), the validity of this method was confirmed.