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Eguchi, Aya; Sagara, Hiroshi*; Mitsuboshi, Natsumi; Nagatani, Taketeru
Dai-46-Kai Nihon Kaku Busshitsu Kanri Gakkai Nenji Taikai Kaigi Rombunshu (Internet), 3 Pages, 2025/12
Eguchi, Aya*; Sagara, Hiroshi*; Mitsuboshi, Natsumi; Nagatani, Taketeru
Dai-45-Kai Nihon Kaku Busshitsu Kanri Gakkai Nenji Taikai Kaigi Rombunshu (Internet), 2 Pages, 2024/11
Advanced fast reactor fuel contains minor actinides and fission products such as lanthanides in addition to uranium and plutonium, and it is supposed to include neutrons and gamma-ray originating from sources other than nuclear materials even in its fresh status. The purpose of this study is to evaluate the applicability of passive neutron nondestructive measurement techniques using coincidence accounting, Differential Die Away Self Interrogation assay technique to the quantification of plutonium in advanced fast reactor fuels. This paper shows the results of Pu-240 effective mass calculation in the Pu neutron sources in the simple simulation design by neutron coincidence accounting for the benchmark of simulation code.
Mitsuboshi, Natsumi; Nagatani, Taketeru; Kosuge, Yoshihiro*; Suzuki, Risa; Okada, Toyofumi
Dai-44-Kai Nihon Kaku Busshitsu Kanri Gakkai Nenji Taikai Kaigi Rombunshu (Internet), 4 Pages, 2023/11
This paper reports the applicability confirmation experiment of DDSI method for quantification of plutonium in fuel debris. We conducted passive neutron measurement for the samples which consist of un-irradiated MOX sample, Cf-252 neutron source, and B-10 neutron absorber to simulate the fuel debris. It was revealed that DDSI method has enough capability to evaluate the leakage multiplication of the sample with unknown amounts of fissile material and neutron absorbers.
Mitsuboshi, Natsumi; Nagatani, Taketeru; Kosuge, Yoshihiro*; Okada, Toyofumi
no journal, ,
This report describes the results of applicability evaluation of the passive neutron technique for determination of the properties of fuel debris or classification of fuel debris and waste of Fukushima Daiichi Nuclear Power Plant site. The applicability of DDSI (Differential Die-Away Self-Interrogation) technique was evaluated to correct the influence of neutron absorber and moderator on neutron counts by the experiment and simulation. For Pu mass evaluation, the applicability of the methodology based on the difference of half-life of Cm-244 and Pu nuclides was also evaluated by the experiment and simulation.
Eguchi, Aya*; Sagara, Hiroshi*; Mitsuboshi, Natsumi; Nagatani, Taketeru
no journal, ,
Mitsuboshi, Natsumi; Nagatani, Taketeru; Kosuge, Yoshihiro*; Okada, Toyofumi
no journal, ,
This report describes the results of applicability evaluation of the passive neutron technique for determination of the properties of fuel debris or classification of fuel debris and waste of Fukushima Daiichi Nuclear Power Plant site. The experiment and simulation revealed the effect of neutron absorber and moderator on neutron counts. The applicability of Pu mass evaluation based on the difference of half-life of Cm-244 and Pu nuclides was also evaluated by the experiment and simulation.
Eguchi, Aya; Sagara, Hiroshi*; Mitsuboshi, Natsumi; Nagatani, Taketeru
no journal, ,
no abstracts in English
Eguchi, Aya*; Sagara, Hiroshi*; Mitsuboshi, Natsumi; Nagatani, Taketeru
no journal, ,
no abstracts in English
Eguchi, Aya*; Sagara, Hiroshi*; Mitsuboshi, Natsumi; Nagatani, Taketeru
no journal, ,