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JAEA Reports

Decommissioning state of Plutonium Fuel Fabrication Facility; Dismantling the glove box W-9 and equipment interior, and a part of tunnel F1

Nagai, Yuya; Shuji, Yoshiyuki; Kawasaki, Takeshi; Aita, Takahiro; Kimura, Yasuhisa; Nemoto, Yasunori*; Onuma, Takeshi*; Tomiyama, Noboru*; Hirano, Koji*; Usui, Yasuhiro*; et al.

JAEA-Technology 2022-039, 117 Pages, 2023/06

JAEA-Technology-2022-039.pdf:11.96MB

Japan Atomic Energy Agency (JAEA) manages wide range of nuclear facilities. Many of these facilities are required to be performed adjustment with the aging and complement with the new regulatory standards and the earthquake resistant, since the Great East Japan Earthquake and the Fukushima Daiichi Nuclear Power Station accident. It is therefore desirable to promote decommissioning of facilities that have reached the end of their productive life in order to reduce risk and maintenance costs. However, the progress of facility decommissioning require large amount of money and radioactive waste storage space. In order to address these issues, JAEA has formulated a "The Medium/Long-Term Management Plan of JAEA Facilities" with three pillars: (1) consolidation and prioritization of facilities, (2) assurance of facility safety, and (3) back-end countermeasures. In this plan, Plutonium Fuel Fabrication Facility has been selected as primary decommissioned facility, and dismantling of equipment in the facilities have been underway. In this report, size reduction activities of the glove box W-9 and a part of tunnel F-1, which was connected to W-9, are presented, and the obtained findings are highlighted. The glovebox W-9 had oxidation & reduction furnace, and pellet crushing machine as equipment interior. The duration of activity took six years from February 2014 to February 2020, including suspended period of 4 years due to the enhanced authorization approval process

JAEA Reports

Operating experiences since rise-to-power test in High Temperature Engineering Test Reactor (HTTR)

Tochio, Daisuke; Watanabe, Shuji; Motegi, Toshihiro; Kawano, Shuichi; Kameyama, Yasuhiko; Sekita, Kenji; Kawasaki, Kozo

JAEA-Technology 2007-014, 62 Pages, 2007/03

JAEA-Technology-2007-014.pdf:9.74MB

The rise-to-power test of the High Temperature Engineering Test Reactor (HTTR) was begun in April 2000. The reactor thermal power of 30 MW, which is the maximum thermal power of the HTTR, and the reactor outlet coolant temperature of 850$$^{circ}$$C in normal operation was achieved in middle of December 2001. After that reactor thermal power of 30 MW a reactor outlet coolant temperature of 950$$^{circ}$$C was achieved in the final rise-to-power test at April 2004. After receiving the operation permit, the safety demonstration tests were conducted to demonstrate inherent safety features of the HTGRs. This paper summarizes the HTTR operating experiences for five years since rise-to-power test that were catalogued into three categories, (1) Operating experience pertaining to new gas cooled reactor design, (2) Operating experience for improvement of the performance, (3) Operating experience due to fail of system and components.

Journal Articles

Antiferromagnetic-to-ferromagnetic transition induced by diluted Co in SrFe$$_{1-x}$$Co$$_x$$O$$_3$$:Magnetic circular X-ray dichroism study

Okamoto, Jun*; Mamiya, Kazutoshi*; Fujimori, Shinichi; Okane, Tetsuo; Saito, Yuji; Muramatsu, Yasuji*; Yoshii, Kenji; Fujimori, Atsushi*; Tanaka, Arata*; Abbate, M.*; et al.

Physical Review B, 71(10), p.104401_1 - 104401_5, 2005/03

 Times Cited Count:20 Percentile:61.99(Materials Science, Multidisciplinary)

The antiferromagnetic-to-ferromagnetic transition in SrFe$$_{1-x}$$Co$$_x$$O$$_3$$ ($$x_c$$$$simeq$$0.15) induced by Co doping has been studied by magnetic circular X-ray dichroism. The orbital and spin magnetic moments of the Fe and Co 3$$d$$ states under the magenetic field of 2 T are found to show different $$x$$ dependences: The spin polarization of Fe 3$$d$$ gradually increases with Co concentration; On the other hand, a large spin polarization of Co 3$$d$$ is induced already in the antiferromagnetic phase, indicating that the Co moment is nearly fully alligned already in the antiferromagnetic phase. This suggests that the alignment of the Fe magnetic moment in SrFe$$_{1-x}$$Co$$_x$$O$$_3$$ is induced by interaction with doped Co magnetic moment. Possible formation of ferromagnetic Co rich region is discussed.

Oral presentation

Study on an application of Powered Air Purifying Respirator (PAPR) half mask to $$alpha$$-ray radiation management at a MOX fuel facility

Tamura, Ken; Hatanaka, Nobuhiro; Nemoto, Shuji; Kimura, Yasuhisa; Hirano, Hiroshi*; Kawasaki, Takashi

no journal, , 

no abstracts in English

Oral presentation

Invention of the magnet-fixing glasses for full-face type respirators

Tamura, Ken; Shuji, Yoshiyuki; Hirano, Hiroshi*; Tachihara, Joji; Ono, Yosuke; Shoji, Hiroyuki*; Kawasaki, Takashi

no journal, , 

no abstracts in English

Patent

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。

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