Evaluation of analysis accuracy in graphite-moderated critical assembly by Monte-Carlo code

Naoki Nakagawa

Presentation information

Oral presentation

III. Fission Energy Engineering » 301-1 Reactor Physics, Utilization of Nuclear Data, Criticality Safety

[1I08-12] Advanced Reactor Development

Mon. Mar 16, 2020 3:35 PM - 5:00 PM Room I (Lecture Bildg. M 2F M-23)

Chair:Tomohiro Endo(Nagoya Univ.)

4:35 PM - 4:50 PM

[1I12] Evaluation of analysis accuracy in graphite-moderated critical assembly by Monte-Carlo code

*Naoki Nakagawa¹, Nozomu Fujimoto¹, Quan Hai Ho², Shimpei Hamamoto², Satoru Nagasumi², Etsuo Ishitsuka² (1. Kyushu Univ., 2. JAEA)

Keywords:HTGR, Monte-Carlo, VHTRC, neutron flux distribution

The accuracy of Monte-Carlo calculations were checked by using VHTRC experiments. As a result, detailed thermal neutron flux distribution in fuel region shows good agreement with experimental value, within 0.75 % error in average. These results shows usability of Monte-Carlo code to evaluation of graphite-moderated system.