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JAEA Reports

Annual report on the environmental radiation monitoring around the Tokai Reprocessing Plant FY2023

Kokubun, Yuji; Hosomi, Kenji; Nagaoka, Mika; Seya, Natsumi; Inoue, Kazumi; Koike, Yuko; Uchiyama, Rei; Sasaki, Kazuki; Maehara, Yushi; Matsuo, Kazuki; et al.

JAEA-Review 2024-054, 168 Pages, 2025/03

JAEA-Review-2024-054.pdf:2.73MB

The Nuclear Fuel Cycle Engineering Laboratories conducts environmental radiation monitoring around the reprocessing plant in accordance with the "Safety Regulations for Reprocessing Plant of JAEA, Part IV: Environmental Monitoring". This report summarizes the results of environmental radiation monitoring conducted during the period from April 2023 to March 2024 and the results of dose calculations for the surrounding public due to the release of radioactive materials from the plant into the atmosphere and ocean. In the results of the above environmental radiation monitoring, several items were affected by radioactive materials emitted from the accident at the Fukushima Daiichi Nuclear Power Station of Tokyo Electric Power Company, Incorporated (changed to Tokyo Electric Power Holdings, Inc. on April 1, 2016), which occurred in March 2011. In addition, environmental monitoring plan, analysis and measurement methods, monitoring data and their chronological change, meteorological data after statistical processing, status of radioactive waste release and evaluation results of the data over the normal range are included as appendices.

Journal Articles

Divertor biasing effects to reduce L/H power threshold in the JFT-2M tokamak

Miura, Yukitoshi; ; ; Hoshino, Katsumichi; ; ; Kasai, Satoshi; Kawakami, Tomohide; Kawashima, Hisato; Maeda, M.*; et al.

Fusion Energy 1996, p.167 - 175, 1997/05

no abstracts in English

Journal Articles

Investigation of causality in the H-L transition on the JFT-2M tokamak

; ; ; ; ; ; ; Oikawa, Toshihiro; ; ; et al.

Fusion Energy 1996, p.885 - 890, 1997/05

no abstracts in English

Oral presentation

Development of safety review method to cope with an aging degradation for the facilities using nuclear material, 2; Risk assessment flow of equipments

Tamaoki, Yuichi; Isozaki, Ryosuke; Suzuki, Ryuta; Akada, Masataka; Sawahata, Satoshi; Yonezawa, Ryoma; Fujishima, Tadatsune; Mizukoshi, Yasutaka; Sakamoto, Naoki

no journal, , 

no abstracts in English

Oral presentation

Development of risk assessment method to cope with an aging degradation for the facilities using nuclear material, 1; Risk point evaluation of aging equipment

Isozaki, Ryosuke; Tamaoki, Yuichi; Suzuki, Ryuta; Akada, Masataka; Sawahata, Satoshi; Suzuki, Hisashi; Yonezawa, Ryoma; Fujishima, Tadatsune; Mizukoshi, Yasutaka; Sakamoto, Naoki

no journal, , 

no abstracts in English

Oral presentation

Development of risk assessment method to cope with an aging degradation for the facilities using nuclear material, 2; Examination of risk assessment method in aging risk assessment

Sawahata, Satoshi; Tamaoki, Yuichi; Isozaki, Ryosuke; Suzuki, Ryuta; Akada, Masataka; Suzuki, Hisashi; Yonezawa, Ryoma; Fujishima, Tadatsune; Mizukoshi, Yasutaka; Sakamoto, Naoki

no journal, , 

no abstracts in English

Oral presentation

Development of risk assessment method to cope with an aging degradation for the facilities using nuclear material, 1; Risk assessment flow of equipments

Tamaoki, Yuichi; Isozaki, Ryosuke; Suzuki, Ryuta; Akada, Masataka; Sawahata, Satoshi; Yonezawa, Ryoma; Suzuki, Hisashi; Mizukoshi, Yasutaka; Sakamoto, Naoki

no journal, , 

The five post-irradiation examination facilities in the Oarai Research and Development Institute of the Japan Atomic Energy Agency have been operated for over 40 years in order to investigate the irradiation performance and physicochemical characteristics of nuclear fuels and materials for fast reactors. The equipments associated with these facilities have been managed to maintain secure from the problems that occurred in the process of aging. Therefore, we established a safety assessment method for aging facilities in 2002, and we have been conducting maintenance management of facilities since then. In this study, designing risk assessment flow is considered in order to solve the issues detected as a result of analysis based on the experience of the repairment during the periodic safety review monitoring.

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