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Tazaki, Makiko
Dai-45-Kai Nihon Kaku Busshitsu Kanri Gakkai Nenji Taikai Kaigi Rombunshu (Internet), 4 Pages, 2024/11
no abstracts in English
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.
Imamura, Yuri
Dai-45-Kai Nihon Kaku Busshitsu Kanri Gakkai Nenji Taikai Kaigi Rombunshu (Internet), 4 Pages, 2024/11
no abstracts in English
Kato, Yuya
Dai-45-Kai Nihon Kaku Busshitsu Kanri Gakkai Nenji Taikai Kaigi Rombunshu (Internet), 4 Pages, 2024/11
no abstracts in English
Oizumi, Akito
Dai-45-Kai Nihon Kaku Busshitsu Kanri Gakkai Nenji Taikai Kaigi Rombunshu (Internet), 4 Pages, 2024/11
When a domestic reprocessing plant starts operation, differences in the estimated Pu amount between the electric utility that manages the discharge of spent MOX fuel from LWRs and the reprocessing plant that received it may affect safeguards reliability. In this study, the uncertainties in the estimated Pu amount caused by nuclear data covariance were quantitatively determined by burn-up sensitivity analysis. In addition, the recommended verification frequency of the Pu amount was discussed by estimating the Pu amount that may be undeclared, using the quantified uncertainty caused by nuclear data covariance. As a result, the quantified uncertainty of the Pu amount caused by the nuclear data covariance was estimated to be 1.58%, and the verification frequency based on this was evaluated once every two weeks or more. More discussion including measurement error is necessary to estimate a more effective verification frequency.
Shimizu, Ryo
Dai-45-Kai Nihon Kaku Busshitsu Kanri Gakkai Nenji Taikai Kaigi Rombunshu (Internet), 4 Pages, 2024/11
no abstracts in English
Koizumi, Mitsuo; Ito, Fumiaki*; Lee, J.; Hironaka, Kota; Takahashi, Tone; Suzuki, Satoshi*; Arikawa, Yasunobu*; Abe, Yuki*; Wei, T.*; Yogo, Akifumi*; et al.
Dai-45-Kai Nihon Kaku Busshitsu Kanri Gakkai Nenji Taikai Kaigi Rombunshu (Internet), 4 Pages, 2024/11