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JAEA Reports

Tritium removal of heavy water system and helium system in FUGEN

Takiya, Hiroaki; Kadowaki, Haruhiko; Matsushima, Akira; Matsuo, Hidehiko; Ishiyama, Masahiro; Aratani, Kenta; Tezuka, Masashi

JAEA-Technology 2020-001, 76 Pages, 2020/05

JAEA-Technology-2020-001.pdf:6.06MB

Advanced Thermal Reactor (ATR) FUGEN was operated for about 25 years, and now has been proceeding decommissioning after the approval of the decommissioning plan in Feb. 2008. The reactor, heavy water system and helium system are contaminated by tritium because of neutron absorption of heavy water, which is a moderator. Before dismantling these facilities, it is necessary to remove tritium from them for not only reducing the amount of tritium released to surrounding environment and the risk of internal exposure by tritium but also ensuring the workability. In first phase of decommissioning (Heavy Water and Other system Decontamination Period), tritium decontamination of the reactor, heavy water system and helium system started in 2008 and completed in 2018. This report shows the results of tritium decontamination of the reactor, heavy water system and helium system.

Journal Articles

Technology demonstration of sampling from reactor core structure of FUGEN Decommissioning Engineering Center

Iwai, Hiroki; Soejima, Goro; Takiya, Hiroaki; Awatani, Yuto; Aratani, Kenta; Miyamoto, Yuta; Tezuka, Masashi

Dekomisshoningu Giho, (61), p.12 - 19, 2020/03

FUGEN Decommissioning Engineering Center received the approval of the decommissioning plan in 2008, and we have been progressing the decommissioning. The first phase of decommissioning (Heavy Water and Other System Decontamination Period) finished in March 2018, and FUGEN has entered into the second phase of decommissioning (Reactor Periphery Facilities Dismantling Period). This report outlines the technology demonstration of sampling from reactor core structure of FUGEN that to prepare for reactor dismantlement in the third phase.

Journal Articles

Status of decommissioning of FUGEN Decommissioning Engineering Center

Takiya, Hiroaki; Aratani, Kenta; Awatani, Yuto; Ishiyama, Masahiro; Tezuka, Masashi; Mizui, Hiroyuki

Dekomisshoningu Giho, (59), p.2 - 12, 2019/03

FUGEN Decommissioning Engineering Center received the approval of the decommissioning program in 2008, and we have been progressing the decommissioning. The first phase of decommissioning (Heavy Water and Other system Decontamination Period) finished in May 2018, and FUGEN has entered into the second phase of decommissioning (Reactor Periphery Facilities Dismantling Period). This report outlines the results obtained in the first phase of decommissioning of FUGEN.

Journal Articles

Pipe cutting method at high radiation area in FUGEN

Takiya, Hiroaki; Ishiyama, Masahiro; Tezuka, Masashi; Kitayama, Naoki

Proceedings of International Conference on Dismantling Challenges; Industrial Reality, Prospects and Feedback Experience (DEM 2018) (Internet), 8 Pages, 2018/10

In FUGEN, we had isolated the reactor core by cutting pipes of the periphery systems (e.g. reactor cooling system, heavy water system, and helium system) between 2015 and 2017, as preparation for dismantling the reactor core and taking some samples from the reactor core structures. There are three issues to be solved at this isolation work; (1) to shorten the working time at high radiation area which is 1-5mSv/h at air and 10mSv/h at contact, (2) to prevent tritium spreading to working area at cutting work because tritium air is existing with 20-30Bq/cm$$^{3}$$ inside of the heavy water system and helium system, and (3) to minimize the influence of contaminated fume for the accurate radioactivity evaluation of reactor core structure. In this study, considering these problems, we discussed the method for cutting the pipes of heavy water system and helium system at the high radiation area and carried out the pipe cutting in the way.

Journal Articles

Preliminary re-conditioning test of the bituminization for radioactive wastes

Soejima, Goro; Takiya, Hiroaki; Mizui, Hiroyuki; Fujita, Yoshihiko*; Akari, Eisaku*; Endo, Nobuyuki*; Kume, Kyo*

Heisei-27-Nendo Koeki Zaidan Hojin Wakasawan Enerugi Kenkyu Senta kenkyu Nempo, 18, P. 14, 2016/10

We have performed the preliminary re-conditioning test of the bituminization for radioactive wastes applying to the technical criteria by non-radioactive samples. As a result, we have confirmed the applicability to secure homogeneity that is a part of the technical criteria by evaluating sample properties.

Journal Articles

Dipole tracer migration and diffusion tests in fractured sedimentary rock at Horonobe URL

Tanaka, Shingo*; Yokota, Hideharu; Ono, Hirokazu; Nakayama, Masashi; Fujita, Tomoo; Takiya, Hiroaki*; Watanabe, Naoko*; Kozaki, Tamotsu*

Proceedings of 23rd International Conference on Nuclear Engineering (ICONE-23) (DVD-ROM), 6 Pages, 2015/05

Oral presentation

Dependence of water diffusion on water to cement ratio in ordinary portland cement pastes

Takiya, Hiroaki*; Tanaka, Shingo*; Noda, Natsuko*; Sato, Seichi*; Kozaki, Tamotsu*; Sato, Haruo; Hatanaka, Koichiro

no journal, , 

It is important to clarify the behaviour of cement porewater for performance assessment of radioactive waste disposal. In this study, we measured apparent self-diffusion coefficients of water in Ordinary Portland Cement pastes with various water-cement ratios (W/C) as the part. The diffusion experiments were carried out as a function of W/C ratio in a range of 0.4-0.8, and O-18 was used as a tracer of water. The apparent diffusion coefficient increased with W/C. All penetration profiles of O-18 showed a tendency to shift from simple diffusion profile with increasing diffusion depth. It was indicated existence of some different diffusion pathways.

Oral presentation

Study on the method for cutting pipes in high radiation area for the isolation of reactor core from other systems in FUGEN

Takiya, Hiroaki; Matsushima, Akira; Ishiyama, Masahiro; Okuzawa, Kazuhiro

no journal, , 

no abstracts in English

Oral presentation

Development of the electrolytic decontamination machine for pipes, 2; Result of decontamination test

Aratani, Kenta; Matsushima, Akira; Takiya, Hiroaki; Awatani, Yuto; Sasaki, Katsuya*; Maehata, Hidehiko*; Maruyama, Akira*

no journal, , 

no abstracts in English

Oral presentation

Trial manufacture of the rubber lining separation machine from rubber-lined pipes

Takiya, Hiroaki

no journal, , 

no abstracts in English

Oral presentation

Specialized training on decommissioning

Matsushima, Akira; Nakayama, Tamotsu; Soejima, Goro; Takiya, Hiroaki; Isomi, Kazuhiko

no journal, , 

no abstracts in English

Oral presentation

Analysis of technical problems on decommissioning work-site activities

Tanabe, Kazuhiro*; Yanagihara, Satoshi*; Iguchi, Yukihiro; Takiya, Hiroaki; Narikawa, Isao*; Kobashi, Hiroaki*; Aoyama, Yoshiharu*; Iida, Keiichi*; Yanagida, Akihiro*; Murayama, Kazunari*; et al.

no journal, , 

In order to make safer and more rational efforts possible for a decommissioning project that is about to begin in full swing, we organized our experience, achievements and knowledge, including maintenance and dismantling work in the plant, and evaluated basic issues for decommissioning.

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