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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

Journal Articles

None

Shuji, Yoshiyuki; Hayashi, Hideyuki

Nihon Genshiryoku Gakkai-Shi, 41(5), p.562 - 570, 1999/00

 Times Cited Count:0 Percentile:0.01(Nuclear Science & Technology)

None

JAEA Reports

None

Onuki, Norihiko; ; Shuji, Yoshiyuki; ; ; ;

PNC TN8410 97-272, 143 Pages, 1997/08

PNC-TN8410-97-272.pdf:5.33MB

None

Journal Articles

Neutronics analysis of a duples-type Mox-Gd fuel in ATR

Yamaguchi, Takashi; Shuji, Yoshiyuki;

Proceedings of ANS Topical Meeting on Advances in Nuclear Fuel Management II, 0 Pages, 1997/00

None

Oral presentation

Measurement examination of Pu content in radioactive waste with portable waste assay system, 1

Ono, Yosuke; Yokoyama, Hitoshi*; Watanabe, Naoki; Miyauchi, Masami; Shuji, Yoshiyuki; Shiota, Yukito; Daidai, Misao

no journal, , 

no abstracts in English

Oral presentation

Measurement examination of Pu content in radioactive waste with portable waste assay system, 2

Ono, Yosuke; Yokoyama, Hitoshi*; Watanabe, Naoki; Miyauchi, Masami; Shuji, Yoshiyuki; Daidai, Misao

no journal, , 

no abstracts in English

Oral presentation

Development of plastic enclosure tents for body contamination

Aita, Takahiro; Hirano, Hiroshi*; Kimura, Yasuhisa; Shibanuma, Tomohiro; Yoshida, Masato; Nagai, Yuya; Asakawa, Jun; Shuji, Yoshiyuki

no journal, , 

The newly developed Plastic enclosure tents have reliable airtightness and can be set up in a short time with the small number of persons. Also, in order to prevent the spread of contamination, the exhaust device secures the internal airflow line, and the radiation management device measures the concentration of radioactive materials in the air are in real time. Furthermore, by setting up a multiple of evacuation routes, the decontamination time is shortened even when there are many contaminated persons. Therefore, it is possible to quickly evacuate the contaminated person by having both radiation safety and setting up that can quickly respond to a large-scale body contamination accident.

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

Oral presentation

An Application of Powered Air Purifying Respirator (PAPR) full-face mask to plutonium handling facilities

Shioya, Satoshi; Nakagawa, Takahiro; Yamazaki, Takumi; Tachihara, Joji; Shuji, Yoshiyuki; Kikuno, Hiroshi

no journal, , 

In order to reduce the workload and improve the safety (i.e., prevention of internal exposure) of workers at Plutonium handling facilities, etc., JAEA has introduced a new Powered Air Purifying Respirator (PAPR) full-face mask as respiratory protective equipment. In introducing this mask, we conducted a leakage test in correspondence with Japanese Industrial Standards (JIS). In the leakage test, an examinee person wearing the mask entered an airlock and performed a prescribed action (e.g., stepping up and down on a stepladder, etc.) while the number concentration of NaCl test particles in/out of the mask was measured. Leakage rates were calculated for the results of 10 examinees. The test results showed that the leakage rate of this mask was $$<$$0.01% (corresponding to the protection factor of $$>$$10000) even when the electric fan was stopped, confirming that the mask remained high protection capability.

Oral presentation

Study on advanced LWR MOX fuel for effective Pu utilization and reduction of spent fuel assemblies

Naganuma, Masayuki; Ikusawa, Yoshihisa; Shuji, Yoshiyuki; Suzuki, Kiichi

no journal, , 

As one of the studies for advancement of LWR MOX fuel, fuel concepts that can contribute to effective plutonium utilization and reduction of spent fuel assemblies in existing reactors were studied. To contribute to this purpose, candidate fuel concepts with the potential to increase the amount of Pu loading in the assembly for PWRs were devised within the current MOX fuel guidelines, and their characteristics were compared and evaluated. As a result, it was found that a fuel type with Gd$$_{2}$$O$$_{3}$$-doped UO$$_{2}$$ fuel pins installed at the assembly corners to adjust the power peaking in the assembly and the reactivity in the BOC is promising and the amount of Pu loading can be increased by approximately 15% compared to the current MOX fuel core. Under the condition that the amount of Pu used for MOX fuel per year is constant, the number of MOX fuel assemblies to be fabricated can be reduced by approximately 15%, therefore, the spent fuel can be also expected to be reduced by the same amount.

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。

Patent

放射線防護マスクの汚染検出方法、フィルタカバー、プレフィルタ治具及びフィルタカバーのセット、及び放射線防護マスク

根本 修直; 田村 健; 周治 愛之; 畑中 延浩; 平野 宏志; 永田 武光

南 明則*

JP, 2019-082129  Patent licensing information  Patent publication (In Japanese)

【課題】迅速、簡便かつ効率的に行うことが可能な放射線防護マスクの汚染検出方法を提供する。 【解決手段】放射線防護マスクの汚染検出方法は、プレフィルタ治具の開口から露出したプレフィルタのα線放出核種捕集量MPREを、α線用サーベイメータで計測する捕集量計測ステップと、α線放出核種捕集量MPREと予め定められた上限値MMAXとを比較する第1比較ステップと、α線放出核種捕集量MPREが上限値MMAX未満の場合に、放射線防護マスクの汚染量が許容範囲内だと判定し、α線放出核種捕集量MPREが上限値MMAX以上の場合に、放射線防護マスクの汚染量が許容範囲を超えていると判定する第1判定ステップとを含む。

Patent

接続テント及び接続テントの組立方法

平野 宏志; 木村 泰久; 柴沼 智博; 會田 貴洋; 永井 佑哉; 浅川 潤; 吉田 将冬; 周治 愛之

南 明則*

JP, 2019-238397  Patent licensing information  Patent publication (In Japanese)

【課題】迅速に組み立て可能な接続テントを提供する。 【解決手段】接続テント(1)は、一対の第1側面フレーム(11、12)及び第1天面フレーム(13)を有する門型フレーム(10)と、第2側面フレーム(21)及び第2天面フレーム(22)を有するL型フレーム(20)と、門型フレーム(10)及びL型フレーム(20)で囲まれた内部空間に収容可能であり、開閉可能な複数の出入口が側面に形成された箱型の部屋テントとを備え、複数の出入口それぞれは、門型フレーム(10)及びL型フレーム(20)の側面に形成された複数の開口のいずれかに対面している。

Patent

ポートキャップ及びグローブボックス

木村 泰久; 平野 宏志; 柴沼 智博; 吉田 将冬; 永井 佑哉; 塙 幸雄; 周治 愛之; 會田 貴洋

南 明則*

JP, 2020-069715  Patent licensing information

【課題】ポート本体とグローブとを間に隙間が生じるのを適切に防止できるポートキャップを提供する。 【解決手段】ポートキャップ(20)は、取付開口(8)から突出する筒体(16)と、先端部が筒体(16)を通じてグローブボックスの内部空間に進入し、基端部が筒体(16)の外周面側に折り返されたグローブ(12)と、折り返されたグローブ(12)と筒体(16)の外周面との間を封止するOリング(13A,13B)及びクランプリング(14)とを備えるグローブポート(10)に取り付けられ、グローブ(12)の内側から筒体(16)に圧入される内筒(21)と、筒体(16)の外側を覆う外筒(22)と、内筒(21)及び外筒(22)の端部同士を接続するフランジ(23)とを備え、内筒(21)の外周面側の先端(21A)は、R面取りされている。

Patent

保持装置

小野 洋輔; 周治 愛之; 平野 宏志; 立原 丈二; 庄司 博行; 田村 健

南 明則*

JP, 2022-000568  Patent licensing information

【課題】全面マスク内で対象物を保持する保持装置において、全面マスクの気密性の維持と、使用者の視界の確保とを両立する技術を提供する。 【解決手段】保持装置(10)は、磁力によって互いに引き合う第1磁性体(11)及び第2磁性体(12)と、対象物を着脱可能に保持する保持部(15)と、第2磁性体(12)から保持部(15)を吊り下げる吊下部(16)とを備える。

15 (Records 1-15 displayed on this page)
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