Presentation Information
[1D03]Quantification of Nuclear Data-Induced Uncertainty and its Reduction using Cross Section Adjustment for a Microreactor
*Kotono NAGATA Nagata1, Tomohiro Endo1, Akio Yamamoto1 (1. Nagoya Univ.)
Keywords:
Microreactor,Uncertainty quantification,Uncertainty reduction,MCNP/Whisper,BeO
The impact of nuclear data uncertainty on a microreactor concept is quantified. Core analyses were performed using the MCNP code. The cross section adjustment was employed to reduce nuclear data-induced uncertainty using the Whisper code. As a result, the 1σ standard deviation of the uncertainty in the effective multiplication factor (k_eff) was reduced by nearly half, from 0.53%Δk/k to 0.28%Δk/k. However, since BeO, which is used in the microreactor, has been rarely used in existing critical experiments, the reduction of BeO nuclear data-induced uncertainty was difficult. Therefore, for further uncertainty reduction, performing new critical experiments or validating the Thermal Scattering Law (TSL) data for BeO by measuring the neutron decay constant would be effective.