2018 Fall Meeting

Presentation information

Oral presentation

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

[1M14-19] Criticality Safety 2

Wed. Sep 5, 2018 4:25 PM - 6:00 PM Room M (E11 -E Building)

Chair:Go Chiba(Hokkaido Univ.)

4:40 PM - 4:55 PM

[1M15] Criticality control technique development for Fukushima Daiichi fuel debris

(46) Criticality benchmark experiment using soluble boron at KUCA.

*YASUHIRO HARADA1, Makoto Nakano1, Kazuya Yamaji1, Tsuyoshi Misawa2, Yasunori Kitamura2 (1. IRID(MHI), 2. Kyoto Univercity)

Keywords:Accident of Fukushima daiichi NPP, melted fuel, debris, ciriticality safety, neutron absorber

When performing critical prevention using solble boron at the time of fuel debris retrieval, a high-concentration boric acid solution may be used from the boron level currently used in the light water reactor.Therefore, it is necessary to carry out the criticality experiment by high concentration borate water, and to perform error evaluation of the critical calculation in a calculation code. The examination using the critical assembly experimental device of Kyoto University Research Reactor Institute was carried out, and the nuclear accuracy of the critical calculation code was checked. In addition, the examination was carried out at 6,000 ppm and 12,000 ppm.