Decommissioning of uranium handling facility for development of nuclear fuel manufacturing equipment

Kageyama, Tomio; Denuma, Akio; Koizumi, Jin*; Odakura, Manabu*; Haginoya, Masahiro*; Isaka, Shinichi*; Kadowaki, Hiroyuki*; Kobayashi, Shingo*; Morimoto, Taisei*; Kato, Yoshiaki*; et al.

JAEA-Technology 2022-033, 130 Pages, 2023/03

JAEA-Technology-2022-033.pdf:9.87MB

Uranium handling facility for development of nuclear fuel manufacturing equipment (Mockup room) was constructed in 1972. The Mockup room has a weak seismic resistance and is deteriorating with age. Also, the original purpose with this facility have been achieved and there are no new development plans using this facility. Therefore, interior equipment installed in this facility had been dismantled and removed since March 2019. After that, the Mockup room was inspected for contamination, and then controlled area in the Mockup room was cancelled on March 29th 2022. A total of 6,549 workers (not including security witnesses) were required for this work. The amount of non-radioactive waste generated by this work was 31,300 kg. The amount of radioactive waste generated by this work was 3,734 kg of combustible waste (103 drums), 4,393 kg of flame resistance waste (61 drums), 37,790 kg of non-combustible waste (124 drums, 19 containers). This report describes about the dismantling and removing the interior equipment in the Mockup room, the amount of waste generated by this work, and procedure for cancellation the controlled area in the facility.

Distance Information Display System using augmented reality for supporting decommissioning work

Miki, Naoya*; Harazono, Yuki*; Ishii, Hirotake*; Shimoda, Hiroshi*; Koda, Yuya

Proceedings of 2nd International Conference on Computer-Human Interaction Research and Applications (CHIRA 2018) (USB Flash Drive), p.134 - 140, 2018/09

https://doi.org/10.5220/0006928601340140

In this study, in order to make measuring lengths of the objects and the gaps at NPPs more efficient, the Distance Information Display System was developed, which make it easy for the dismantling workers to measure them. The results showed that the Distance Information Display System developed in this study can be used easily with extremely simple operation by the dismantling workers at NPPs, and the workers can also measure the lengths in a short time.

Decommissioning nuclear facilities in safety

Tanaka, Mitsugu

Gijutsu To Keizai, (412), p.46 - 51, 2001/06

https://ci.nii.ac.jp/naid/40003944020

no abstracts in English

Measures of closing report of outside waste storage pits

; Ishibashi, Yuzo; Yoshida, Michihiro; Miyo, Hiroaki; Sukegawa, Yasuhiro*; *; Suzuki, Satoshi*

JNC TN8440 2000-020, 500 Pages, 2000/10

JNC-TN8440-2000-020.pdf:25.91MB

At outside waste storage pits, containers for storage of wastes corroded and were flooded, and it was confirmed on August 26, 1997. Confirmation of contamination of the pits outskirts, installation of sheets to prevent rainwater from flowing into the pits, drawing stay water were executed, promptly. Design and authorization works of the work house and waste treatment devices to take out wastes of the pits were executed too. After construction of the work house, taking out wastes of the pits started, and finished on April 10, 1998. Investigations of the inflow point of rainwater and leak of stay water were executed next. The results were reported to Science and Thechnology Agency (STA), adjoining authorities on December 21, 1998. After decontamination of the pits inner walls to background level of the radioactivity which included general concrete, control area was removed, and the pits were closed by concrete. Measures of closing of the pits were prepared from the middle of August, 1999, and dismantlement of unnecessary instruments started. Decontamination of the pits started from the begining of September, 1999. The above works finished on June 30, 2000. After decontamination of the pits, STA, adjoining authorities confirmed the circumstances. Work pouring concrete into the pits was executed three times (three levels), and finished on August 31, 2000. In addition t0 above, the amount of concrete poured into the pits was about 1,200 m.

Disassembly and removal of 50MW steam generator test facility; Disassembly and sodium removal of the large cold trap

JNC TN9410 2000-003, 52 Pages, 1999/12

JNC-TN9410-2000-003.pdf:3.51MB

In May, 1999, disassembly and cleansing of sodium residues contained in the large cold trap (50MWSG) were carried out. Two cold trap units, one from the primary sodium loop and the other from the for the secondary sodium loop were disassembled and cleaned. This report describes the procedures, methods, and tasks under taken in the clean-up effort, including countermeasures for safe handling of sodium. The disassembly of the cold trap was based an information regarding similar cleansing activities external to JNC. There was also same a priori knowledge of the type and amount of sodium-laden residues. As this result, we conducted disassembly and cleansing task as provisionally planned. In fact we learned that disassembly methods for the specific components could be conducted in an aerated atmosphere. We thus gained additional disassembly and sodium cleansing experience under manageable and safe conditions.

Completion of the Japan Power Demonstration Reactor decommissioning program; Experience and waste management

Miyasaka, Yasuhiko; Tanaka, Mitsugu

10th Pacific Basin Nuclear Conf. (10-PBNC), 2, p.1223 - 1230, 1996/00

no abstracts in English

Current status of Fugen decommissioning Project and my work

Koda, Yuya

no journal, , 

no abstracts in English

Dismantlement status and future plans in FUGEN

Aratani, Kenta; Ishiyama, Masahiro; Awatani, Yuto; Miyamoto, Yuta; Tezuka, Masashi

no journal, , 

no abstracts in English

物品搬出入システム及び物品搬出入方法

吉田 将冬; 周治 愛之; 川崎 猛; 木村 泰久; 平野 宏志

not registered

JP, 2018-170691  Patent licensing information  Patent publication (In Japanese)

【課題】汚染雰囲気に曝される物を最小限に抑えて、汚染雰囲気に対して物品を安全に搬出入可能な物品搬出入システムを提供する。 【解決手段】物品搬出入システムは、汚染雰囲気を囲って非汚染雰囲気から隔離すると共に、汚染雰囲気及び非汚染雰囲気を連通させる開口が形成されたポートを有する建屋と、物品が載置される載置部、及び把持可能な把持部を有する載置台と、可撓性を有する材料で構成されており、開放された両端部のうち、一方側端部が前記開口を囲むようにポートに接続され、他方側端部が載置部を囲むように載置台に接続される筒状部材と、筒状部材から露出した把持部を把持して、ポートを通じて載置台を建屋に搬入し、さらに建屋から搬出する搬出入装置と、載置台が建屋から搬出された後に、ポートと載置台との間で筒状部材をシールするシール装置とを備えることを特徴とする。