Comparison between simulation and experimental results for neutron flux in DDA systems

DDAシステム内中性子束分布に対するシミュレーション結果と実験値の比較

前田 亮  ; 米田 政夫   ; 大図 章  ; 呉田 昌俊   ; 藤 暢輔   ; Bogucarska, T.*; Crochemore, J. M.*; Varasano, G.*; Pedersen, B.*

Maeda, Makoto; Komeda, Masao; Ozu, Akira; Kureta, Masatoshi; Toh, Yosuke; Bogucarska, T.*; Crochemore, J. M.*; Varasano, G.*; Pedersen, B.*

JAEA and EC/JRC have been carrying out collaborative research for developing new non-destructive assay techniques that can be utilized for quantifying high radioactive special nuclear materials such as spent fuel and next generation minor actinide fuels. In the research, accuracy of Monte Carlo simulation is important since it is utilized for design and development of a demonstration system of next-generation Differential Die-away (DDA) technique in JAEA. In order to evaluate the accuracy, neutron flux in the sample cavity of the PUNITA device which utilizes JRC type DDA technique and one of JAWAS-T device which utilizes JAEA type DDA technique were measured. The neutron flux in the target sample placed in the PUNITA sample cavity was also measured. The measurement results were compared with the simulation results. In this presentation, we report on comparison results for the neutron flux obtained by experiment and simulation.