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JAEA Reports

Annual report on the environmental radiation monitoring around the Tokai Reprocessing Plant FY2022

Kokubun, Yuji; Nakada, Akira; Seya, Natsumi; Koike, Yuko; Nemoto, Masashi; Tobita, Keiji; Yamada, Ryohei*; Uchiyama, Rei; Yamashita, Daichi; Nagai, Shinji; et al.

JAEA-Review 2023-046, 164 Pages, 2024/03

JAEA-Review-2023-046.pdf:4.2MB

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 2022 to March 2023 and the results of dose calculations for the surrounding public due to the release of radioactive materials into the atmosphere and ocean. In the results of the above environmental radiation monitoring, many items were affected by radioactive materials emitted from the accident at the Fukushima Daiichi Nuclear Power Plant of Tokyo Electric Power Company, Incorporated (changed to Tokyo Electric Power Company Holdings, Inc. on April 1, 2016), which occurred in March 2011. Also included as appendices are an overview of the environmental monitoring plan, an overview of measurement methods, measurement results and their changes over time, meteorological statistics results, radioactive waste release status, and an evaluation of the data which deviated of the normal range.

JAEA Reports

Annual report on the environmental radiation monitoring around the Tokai Reprocessing Plant FY2021

Nakada, Akira; Kanai, Katsuta; Seya, Natsumi; Nishimura, Shusaku; Futagawa, Kazuo; Nemoto, Masashi; Tobita, Keiji; Yamada, Ryohei*; Uchiyama, Rei; Yamashita, Daichi; et al.

JAEA-Review 2022-078, 164 Pages, 2023/03

JAEA-Review-2022-078.pdf:2.64MB

Environmental radiation monitoring around the Tokai Reprocessing Plant has been performed by the Nuclear Fuel Cycle Engineering Laboratories, based on "Safety Regulations for the Reprocessing Plant of Japan Atomic Energy Agency, Chapter IV - Environmental Monitoring". This annual report presents the results of the environmental monitoring and the dose estimation to the hypothetical inhabitant due to the radioactivity discharged from the plant to the atmosphere and the sea during April 2021 to March 2022. In this report, some data include the influence of the accidental release from the Fukushima Daiichi Nuclear Power Station of Tokyo Electric Power Co., Inc. (the trade name was changed to Tokyo Electric Power Company Holdings, Inc. on April 1, 2016) in March 2011. Appendices present comprehensive information, such as monitoring programs, monitoring methods, monitoring results and their trends, meteorological data and discharged radioactive wastes. In addition, the data which were influenced by the accidental release and exceeded the normal range of fluctuation in the monitoring, were evaluated.

JAEA Reports

Annual report on the environmental radiation monitoring around the Tokai Reprocessing Plant FY2020

Nakada, Akira; Nakano, Masanao; Kanai, Katsuta; Seya, Natsumi; Nishimura, Shusaku; Nemoto, Masashi; Tobita, Keiji; Futagawa, Kazuo; Yamada, Ryohei; Uchiyama, Rei; et al.

JAEA-Review 2021-062, 163 Pages, 2022/02

JAEA-Review-2021-062.pdf:2.87MB

Environmental radiation monitoring around the Tokai Reprocessing Plant has been performed by the Nuclear Fuel Cycle Engineering Laboratories, based on "Safety Regulations for the Reprocessing Plant of Japan Atomic Energy Agency, Chapter IV - Environmental Monitoring". This annual report presents the results of the environmental monitoring and the dose estimation to the hypothetical inhabitant due to the radioactivity discharged from the plant to the atmosphere and the sea during April 2020 to March 2021. In this report, some data include the influence of the accidental release from the Fukushima Daiichi Nuclear Power Station of Tokyo Electric Power Co., Inc. (the trade name was changed to Tokyo Electric Power Company Holdings, Inc. on April 1, 2016) in March 2011. Appendices present comprehensive information, such as monitoring programs, monitoring methods, monitoring results and their trends, meteorological data and discharged radioactive wastes. In addition, the data which were influenced by the accidental release and exceeded the normal range of fluctuation in the monitoring, were evaluated.

JAEA Reports

Manufacture of substitutive assemblies for MONJU reactor decommissioning

Sakakibara, Hiroshi; Aoki, Nobuhiro; Muto, Masahiro; Otabe, Jun; Takahashi, Kenji*; Fujita, Naoyuki*; Hiyama, Kazuhiko*; Suzuki, Hirokazu*; Kamogawa, Toshiyuki*; Yokosuka, Toru*; et al.

JAEA-Technology 2020-020, 73 Pages, 2021/03

JAEA-Technology-2020-020.pdf:8.26MB

The decommissioning is currently in progress at the prototype fast breeder reactor Monju. Fuel assemblies will be taken out of its core for the first step of the great task. Fuel assemblies stand on their own spike plugged into a socket on the core support plate and support with adjacent assemblies through their housing pads each other, resulting in steady core structure. For this reason, some substitutive assemblies are necessary for the purpose of discharging the fuel assemblies of the core. Monju side commissioned, therefore, Plutonium Fuel Development Center to manufacture the substitutive assemblies and the Center accepted it. This report gives descriptions of design, manufacture, and shipment in regard to the substitutive assemblies.

JAEA Reports

Annual report on the environmental radiation monitoring around the Tokai Reprocessing Plant FY2019

Nakano, Masanao; Fujii, Tomoko; Nemoto, Masashi; Tobita, Keiji; Seya, Natsumi; Nishimura, Shusaku; Hosomi, Kenji; Nagaoka, Mika; Yokoyama, Hiroya; Matsubara, Natsumi; et al.

JAEA-Review 2020-069, 163 Pages, 2021/02

JAEA-Review-2020-069.pdf:4.78MB

Environmental radiation monitoring around the Tokai Reprocessing Plant has been performed by the Nuclear Fuel Cycle Engineering Laboratories, based on "Safety Regulations for the Reprocessing Plant of Japan Atomic Energy Agency, Chapter IV - Environmental Monitoring". This annual report presents the results of the environmental monitoring and the dose estimation to the hypothetical inhabitant due to the radioactivity discharged from the plant to the atmosphere and the sea during April 2019 to March 2020. In this report, some data include the influence of the accidental release from the Fukushima Daiichi Nuclear Power Station of Tokyo Electric Power Co., Inc. (the trade name was changed to Tokyo Electric Power Company Holdings, Inc. on April 1, 2016) in March 2011. Appendices present comprehensive information, such as monitoring programs, monitoring methods, monitoring results and their trends, meteorological data and discharged radioactive wastes. In addition, the data which were influenced by the accidental release and exceeded the normal range of fluctuation in the monitoring, were evaluated.

JAEA Reports

Study for process and equipment design of wet gelation stages in vibropacking process

*; *; *; *; *; *

JNC TJ9400 2003-002, 142 Pages, 2003/02

JNC-TJ9400-2003-002.pdf:5.5MB

Process and layout design of external wet gelation stages in vibropacking process was examined for the feasibility study of commercialized FBR cycle system. In this study, solidification, washing, drying, calcination, reduction, sintering stages including interim storage of sintering particles for the oxide core fuel production line were selected. The main results obtained by this study are as follows: (1)Based on the process examination results conducted last year, process-flow, mass balance and number of production line/equipment included sintering and interim storage stage were clarified. (2)On the basis of equipment layout examination, criticality safety considerations were sort out taking into account of abnormal conditions, such as leakage of particles onto the floor and apparatus-container mutual interference during container transfer. (3)Preliminary design of the main equipment was done. Equipment layout design was done in consideration of material transfer flow and maintenance measures to be applied. A schematic layout drawing was presented and a maintenance procedure was arranged along with a time scheduling. (4)Analytical sample taking points and necessary analytical items were extracted taking into account of quality control and process management. (5)A feature of the operating rate at each process stage was sort by examining a failure rate reliability of each component. (6)Based on the results, utility consumed and number of operators required for the plant operation, an amount of wastes was evaluated. (7)Equipment cost was evaluated for the production capacity of 200 ton-HM/year and capacity-cost interrelation dependency was examined in the view of number of production line.

JAEA Reports

Test manufacturing study of copper canisters for composite overpack

*; *; *; *

JNC TJ8400 99-049, 28 Pages, 1999/02

JNC-TJ8400-99-049.pdf:1.44MB

In study and development of high-level radioactive waste geological disposal, engineering study is being carried out on design, manufacturing, and installation of the engineering barrier to clarify the engineering method that can ensure performances necessary for the engineering barrier. For the overpack, which is one of composition elements of the engineering barrier, at present there are two conceptions; i.e. a carbon steel overpack (of simplex carbon steel construction) and a composite overpack (of two-layer construction having a carbon steel inside for strength and titanium, copper, or others outside for corrosion resistant). Studies are being carried out on them from the viewpoints of their respective functions and manufacturing. For the carbon steel overpack, development elements in manufacturing technology have already been extracted through manufacturing full-scale models. In this entrusted study, we carried out some tests to obtain informations about applicability of some manufacturing method, through manufacturing of full-scale copper canister model which established in the manufacturing method study of last year.

JAEA Reports

Test manufacturing study of copper canisters for composite overpack

*; *; *; *

JNC TJ8400 99-048, 74 Pages, 1999/02

JNC-TJ8400-99-048.pdf:9.66MB

In study and development of high-level radioactive waste geological disposal, engineering study is being carried out on design, manufacturing, and installation of the engineering barrier to clarify the engineering method that can ensure performances necessary for the engineering barrier. For the overpack, which is one of composition elements of the engineering barrier, at present there are two conceptions; i.e. a carbon steel overpack (of simplex carbon steel construction) and a composite overpack (of two-layer construction having a carbon steel inside for strength and titanium, copper or others outside for corrosion resistant). Studies are being carried out on them from the viewpoints of their respective functions and manufacturing. With respect to the carbon steel overpack, development elements in manufacturing technology have already been extracted through manufacturing full-scale models. In this entrusted study, we carried out some tests to obtain informations about applicability of some manufacturing method, through manufacturing of full-scale copper canister model which established in the manufacturing method study of last year.

Journal Articles

Replacement of pressure surge tank and vent valves in JMTR

Ishii, Toshimitsu; Ooka, Norikazu; Saito, Junichi; Kobayashi, Shunichi; Takahashi, Kunihiro; Tsukada, Takashi; Iwai, Takashi; Kurosawa, Yoshiaki; Hoshiya, Taiji; Tsuji, Hirokazu

Proceedings of International Symposium on Case Histories on Integrity and Failures in Industry (CHIFI), p.227 - 236, 1999/00

no abstracts in English

Journal Articles

Effect of microstructure and strength of low alloy steels on cyclic crack growth in high temperature water

*; Nakajima, Hajime; ; ; Kondo, Tatsuo

Corrosion Fatigue; Mechanics, Metallurgy, Electrochemistry and Engineering, p.256 - 286, 1983/00

no abstracts in English

JAEA Reports

Cyclic Crack Growth Typical Weld HAZ Microstructures of SA 533gr.B Steel in Simulated BWR Environment

; ; Shindo, Masami; ; ; ; ; ; *; *; et al.

JAERI-M 82-062, 23 Pages, 1982/06

JAERI-M-82-062.pdf:1.31MB

no abstracts in English

Journal Articles

Fatigue crack growth through typical weld HAZ(heat affected zone)microstructures of SA 533 Gr.B steel in BWR primary coolant.

Nakajima, Hajime; *; ; *; Kondo, Tatsuo

Zairyo, 31(346), p.710 - 716, 1982/00

no abstracts in English

Oral presentation

The In-situ verification of performance of engineered barrier system in Horonobe Underground Research Laboratory, 12; Study of quality control method on the in-situ compaction technique for backfilling

Tanai, Kenji; Kikuchi, Hirohito*; Nakayama, Masashi; Ono, Hirokazu; Shirase, Mitsuyasu*; Takahashi, Akihiro*; Niunoya, Sumio*; Kuriyama, Masanori*

no journal, , 

no abstracts in English

Oral presentation

Evaluation of safety function affected by long-term evolution of sealing system, 2; Scenario development

Mitsuyama, Kazuaki*; Takeda, Masaki; Sugita, Yutaka; Ono, Hirokazu; Wakasugi, Keiichiro*; Takase, Hiroyasu*; Takahashi, Hirokazu*; Hashimoto, Tomoko*

no journal, , 

no abstracts in English

Oral presentation

Evaluation of safety function affected by long-term evolution of sealing system, 3; Transport modeling

Takahashi, Hirokazu*; Takeda, Masaki; Sugita, Yutaka; Ono, Hirokazu; Wakasugi, Keiichiro*; Takase, Hiroyasu*; Mitsuyama, Kazuaki*; Hashimoto, Tomoko*

no journal, , 

no abstracts in English

Oral presentation

Design and manufacture of substitutive assemblies for MONJU reactor decommissioning

Sakakibara, Hiroshi; Aoki, Nobuhiro; Muto, Masahiro; Otabe, Jun; Takahashi, Kenji*; Fujita, Naoyuki*; Hiyama, Kazuhiko*; Suzuki, Hirokazu*; Kamogawa, Toshiyuki*; Yokosuka, Toru*; et al.

no journal, , 

no abstracts in English

16 (Records 1-16 displayed on this page)
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