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JAEA Reports

Analysis work report on removal of spent fuel sheared powder for decommissioning of main plant

Aoya, Juri; Mori, Amami; Sato, Hinata; Kono, Soma; Morokado, Shiori; Horigome, Kazushi; Goto, Yuichi; Yamamoto, Masahiko; Taguchi, Shigeo

JAEA-Technology 2023-008, 34 Pages, 2023/06

JAEA-Technology-2023-008.pdf:1.92MB

Flush-out, by which nuclear materials in the Tokai Reprocessing Plant process are recovered, has been started in June 2022 as the first step of decommissioning. Flush-out consists of removal of spent fuel sheared powder, plutonium solution, uranium solution, and the other nuclear materials. Removal of spent fuel sheared powder has been completed in September 2022. During removal of spent fuel sheared powder, uranium concentration, plutonium concentration, acid concentration, radioactivity concentration, and solution density have been analyzed for process control. For nuclear material accountancy, uranium concentration, plutonium concentration, isotope ratio, and solution density have been analyzed. Analysis work including sample pretreatment before transportation to IAEA analytical facility for safeguards, and the other operations related to Flush-out such as calibration of analytical instruments, education, and training of operators are reported.

Journal Articles

Development of training course on non-destructive assay of nuclear material for Asian region, 2; Development of lectures and exercises on gamma-ray measurement

Yamamoto, Masahiko; Kono, Soma; Saegusa, Yu; Kuno, Takehiko; Sekine, Megumi; Inoue, Naoko; Noro, Naoko; Rodriguez, D.; Yamaguchi, Tomoki; Stinett, J.*

Proceedings of INMM & ESARDA Joint Annual Meeting 2023 (Internet), 10 Pages, 2023/05

The gamma-ray measurement part of the Non-Destructive Assay (NDA) course of safeguards and nuclear material accountancy was developed to focus on gamma-ray measurement allotting two days out of five days. The lectures on the basic characteristics and detection methods and mechanism of gamma-ray detectors were provided as e-learnings which were developed. The part for hands-on exercises were implemented in JAEA facility. Participants have set up each gamma-ray detector, and performed measurements of uranium and the other gamma-ray emitting nuclides. Also, uranium-235 enrichment measurements have been performed. In addition, the participants trained with a handheld gamma-ray spectrometer, HM-5, that is popular for IAEA safeguards as the preparation in the measurement exercise of fresh fuel assemblies in JRR-3, a research reactor facility of JAEA. This paper reports on the development, implementation, and feedback from participants on gamma-ray measurement part of the NDA course.

Journal Articles

Security measures at nuclear fuel facilities, 2; Internal threat countermeasure in cyber-security

Kono, Soma; Yamada, Hiroyuki; Goto, Atsushi*; Yamazaki, Katsuyuki; Nakamura, Hironobu; Kitao, Takahiko

Nihon Kaku Busshitsu Kanri Gakkai Dai-39-Kai Nenji Taikai Rombunshu (Internet), 2 Pages, 2018/11

no abstracts in English

Journal Articles

Discussion of effective insider threat mitigation method at reprocessing plant

Nakamura, Hironobu; Kitao, Takahiko; Yamada, Hiroyuki; Kono, Soma; Kimura, Takashi; Tasaki, Takashi

Proceedings of INMM 59th Annual Meeting (Internet), 9 Pages, 2018/07

Oral presentation

Nuclear security measures at nuclear fuel facilities, 1; Trust worthiness program for insider mitigation method

Yamada, Hiroyuki; Kono, Soma; Tasaki, Takashi; Kojima, Junji; Kitao, Takahiko; Nakamura, Hironobu

no journal, , 

no abstracts in English

Oral presentation

Development of sodium determination in high active liquid waste using ion selective electrode

Aoya, Juri; Kono, Soma; Yamamoto, Masahiko; Inada, Satoshi; Kuno, Takehiko

no journal, , 

Vitrification of high active liquid waste (HALW) is a top priority toward the decommissioning of Tokai Reprocessing Plant. Concentration of Sodium (Na) in HALW is required to be analyzed accurately and quickly for the vitrification process control, because it affects viscosity of molten glass and element leaching rate from the vitrified waste. An inductively coupled plasma optical emission spectrometer (ICP-OES), which is modified for remote operation by manipulator in the hot cell, is used for determination of Na in HALW. However, the trouble of the ICP-OES generally requires long recovery time and causes possibility of the vitrification process delay. Therefore, for alternative determination method to prevent the vitrification process delay, Na determination method in HALW using Na-ion selective electrode, which measures electromotive force generated in accordance with ion concentration in solution sample is developed. In this study, influences by hydrogen ion (H$$^{+}$$) and the other coexistent elements on analytical performance, and measurement results of Na in HALW by the ion selective electrode are reported.

Oral presentation

Applicability evaluation of uranium and plutonium analysis by a handheld X-ray fluorescence analyzer

Kono, Soma; Horigome, Kazushi; Yamamoto, Masahiko; Taguchi, Shigeo

no journal, , 

no abstracts in English

Oral presentation

Oral presentation

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