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Kyffin, J.*; Dia, A.*; Nkosi, G.*; Nizhnik, V.*; Hayashi, Akihiko; Nagatani, Taketeru
Proceedings of 65th Annual Meeting of the Institute of Nuclear Materials Management (Internet), 8 Pages, 2024/07
Kato, Akane; Shirafuji, Masaya; Suekane, Yurika; Shimizu, Yasuyuki; Kitao, Takahiko
Proceedings of 65th Annual Meeting of the Institute of Nuclear Materials Management (Internet), 9 Pages, 2024/07
Tokai Reprocessing Plant (TRP) started to recover those remaining nuclear materials from main process in reprocessing facility (Flush-out) as a first step of decommissioning. Flush-out plan is conducted by three steps for recovering sheared powder (Stage A), Pu (Stage B) and U (Stage C). Stage A for recovering sheared powder was implemented from June to September 2022. As the next step of Flush-out plan, Stage B and Stage C, were implemented from March 2023 in stepwise. Stage B is to transfer Pu solution from storage material balance area (MBA) to HALW storage as retained waste, and stage C is to fabricate Uranium trioxide powder from U solution. Since these activities for flush-out are different from conventional reprocessing operation, TRP should overcome the subject for the establishment of appropriate material control and accountancy (MC&A) method and new safeguards measures implemented by IAEA. In this paper, we report about Pu and U recovery process and relevant MC&A and safeguards measures in the Flush-out.
Rossi, F.; Lee, J.; Kodama, Yu; Hironaka, Kota; Koizumi, Mitsuo; Hori, Junichi*; Terada, Kazushi*; Sano, Tadafumi*
Proceedings of 65th Annual Meeting of the Institute of Nuclear Materials Management (Internet), 8 Pages, 2024/07
Rodriguez, D. C.; Akamatsu, Shunsuke*; Rossi, F.; Suzuki, Satoshi*; Takahashi, Tone
Proceedings of 65th Annual Meeting of the Institute of Nuclear Materials Management (Internet), 9 Pages, 2024/07
Broughton, D.*; Suzuki, Risa; Nagatani, Taketeru; Okada, Toyofumi; Henzlova, D.*; Longo, J.*; Mendez, J.*; Rael, C.*; Swinhoe, M. T.*
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This presentation will discuss issues and potential improvements in the measurement of nuclear material generated from ongoing decommissioning activities at JAEA facilities. This material is subject to safeguards requirements, but its high impurity content makes it difficult to measure using standard deployed NDA systems.