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JAEA Reports

Document collection of the 37th Technical Special Committee on Fugen Decommissioning

Nakamura, Yasuyuki; Koda, Yuya; Yamamoto, Kosuke; Soejima, Goro; Iguchi, Yukihiro

JAEA-Review 2020-002, 40 Pages, 2020/05

JAEA-Review-2020-002.pdf:8.78MB

Fugen Decommissioning Engineering Center, in planning and carrying out our decommissioning technical development, has been establishing "Technical special committee on Fugen decommissioning" which consists of the members well-informed, aiming to make good use of Fugen as a place for technological development which is opened inside and outside the country, as the central point in the energy research and development base making project of Fukui prefecture, and to utilize the outcome in our decommissioning to the technical development effectively. This report compiles presentation materials "The Current Situation of Fugen Decommissioning", "Development of Dismantling Mon-hours Estimated system by Achieved Data in Fugen", "Future Plan Based on the Operational Status of Clearance System" and "The Result and Future Plan of the Sampling work from Core Internal of Fugen", presented in the 37th Technical special committee on Fugen decommissioning which was held on December 2, 2019.

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

Laser cutting underwater is carried out in the Fukui Smart Decommissioning Technology Demonstration Base

Soejima, Goro; Iwai, Hiroki; Nakamura, Yasuyuki; Kuwamuro, Naotoshi*; Shimazu, Tadashi*

Eneken Nyusu (Internet), 131, P. 1, 2019/04

We investigated the behavior of the dust generated by Laser cutting underwater aimed at the simulant material of reactor components (SUS304) and the pressure and calandria tube (Zr-2.5%Nb, Zry-2) of the prototype reactor. This test was carried out in the water tank as large as the reactor of FUGEN.

Journal Articles

Investigation for dust behavior of cutting in air and cutting underwater by thermal cutting methods

Soejima, Goro; Iwai, Hiroki; Nakamura, Yasuyuki; Tsuzuki, Satoshi*; Yasunaga, Kazushi*; Kume, Kyo*

Heisei-29-Nendo Koeki Zaidan Hojin Wakasawan Enerugi Kenkyu Senta kenkyu Nempo, 20, P. 80, 2018/11

We investigated the behavior of the dust generated by Laser and Plasma-arc cutting underwater and in air aimed at the simulant material of reactor components (SUS304) and the pressure and calandria tube (Zr-2.5%Nb, Zry-2) of the prototype reactor "FUGEN".

Journal Articles

Study of the dust behavior on the laser and plasma cutting

Soejima, Goro; Iwai, Hiroki; Kadowaki, Haruhiko; Nakamura, Yasuyuki; Tsuzuki, Satoshi*; Yasunaga, Kazushi*; Nakata, Yoshinori*; Kume, Kyo*

Heisei-28-Nendo Koeki Zaidan Hojin Wakasawan Enerugi Kenkyu Senta kenkyu Nempo, 19, P. 9, 2017/10

no abstracts in English

Journal Articles

Technology development on reactor dismantling and investigation of contamination in FUGEN

Soejima, Goro; Iwai, Hiroki; Nakamura, Yasuyuki; Hayashi, Hirokazu; Kadowaki, Haruhiko; Mizui, Hiroyuki; Sano, Kazuya

Proceedings of 25th International Conference on Nuclear Engineering (ICONE-25) (CD-ROM), 5 Pages, 2017/07

no abstracts in English

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

Application of measurement and evaluation method on the clearance system of the Fugen NPP for dismantled equipment of turbine system

Hayashi, Hirokazu; Soejima, Goro; Mizui, Hiroyuki; Sano, Kazuya

Proceedings of 23rd International Conference on Nuclear Engineering (ICONE-23) (DVD-ROM), 7 Pages, 2015/05

In the Fugen Nuclear Power Plant, we are going to conduct appropriate classification of the waste according to the contamination level of the material of the plant, to reduce the amount of radioactive waste and to promote dismantling work rationally and efficiently. For this reason, we are going to apply the clearance system to the dismantled material generated from dismantling work of the turbine system, and to reduce the radioactive waste amount as much as possible. In order to operate the clearance system properly, the target nuclides need to be selected accurately, and the evaluation method of them should be established. The assessment was conducted as follows.

Patent

放射能評価方法、放射能評価プログラム及び放射能評価装置

水井 宏之; 林 宏一; 副島 吾郎; 岩井 紘基; 山本 耕輔

not registered

JP, 2020-042714  Patent licensing information  Patent publication (In Japanese)

【課題】冷却材に含まれるCP核種及びFP核種の放射能濃度を適切に評価することができる放射能評価方法を提供する。 【解決手段】冷却材Wに含まれる核種Xの放射能濃度DXを評価する放射能評価方法は、冷却系構造材起因の核種Xの第1の放射能濃度D1Xを評価する第1の評価工程(S1)と、第1の放射能濃度とFP核種補正項とに基づいて、核燃料物質起因の核種の第2の放射能濃度D2Xを評価する第2の評価工程(S2)と、第1の放射能濃度D1Xと第2の放射能濃度D2Xとに基づいて、核種Xの放射能濃度DXを評価する第3の評価工程(S3)とを含む。第2の評価工程では、冷却材濃度測定データと所定の汎用放射化解析コードによる放射能濃度とを用いてFP核種補正係数を算定し、冷却系構造材起因の核種の放射能濃度と冷却系構造材が含有する核燃料物質起因の核種の放射能濃度とを用いてFP寄与割合を算出し、FP核種補正項を算定する。

Patent

放射化汚染の放射能評価の際の評価対象となる核種の選定方法

林 宏一; 水井 宏之; 副島 吾郎; 岩井 紘基

not registered

JP, 2020-060021  Patent licensing information  Patent publication (In Japanese)

【課題】原子炉等の廃止措置において扱われる廃棄物に対するクリアランス判定に際して、評価の対象とすべき核種を、安全性を確保しつつ簡易に選定する。 【解決手段】全ての核種についてDKが算出される(S1)。次に、全てのDKに基づいてQ0が、重要核種(10種)のDKのみに基づいてQ1が選定のための指標値としてそれぞれ算出される(S2:算出工程)。Q1/Q0≧0.9でない場合(S3:NO)には、重要核種(10種)以外の核種の寄与が無視できないと認識されるため、重要核種以外で、DK/CKが大きな核種をDK/CKの大きな順に選定し、ここで追加された核種が、重要核種(10種)に加えて選定される(S7:選定工程)。DKの算出に際して、重要核種(10種類)に対しては下限側代表値が、重要核種以外の核種(23種類)に対しては上限側代表値)が、各元素の組成の代表値として用いられる。

Oral presentation

Trial production of the sampling tool from the pipe

Hayashi, Hirokazu; Soejima, Goro; Mizui, Hiroyuki; Sano, Kazuya

no journal, , 

no abstracts in English

Oral presentation

The Laser cutting test for the dust behavior research in the cutting work of the nuclear facility in air

Soejima, Goro; Iwai, Hiroki; Mori, Naoto; Sano, Kazuya; Morishita, Yoshitsugu

no journal, , 

no abstracts in English

Oral presentation

Evaluation of the cutting and dust generation of simulant material of reactor pressure vessel by 30 kW fiber laser

Kadowaki, Haruhiko*; Ishigami, Ryoya*; Soejima, Goro; Iwai, Hiroki; Nakamura, Yasuyuki

no journal, , 

no abstracts in English

Oral presentation

Technology survey on in-situ simple $$gamma$$ ray measurement

Soejima, Goro; Kadowaki, Haruhiko; Iwai, Hiroki; Nakamura, Yasuyuki; Mizui, Hiroyuki; Sano, Kazuya

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

Specialized training on decommissyoninng

Hayashi, Shoichi; Matsushima, Akira; Kawagoe, Shinji; Soejima, Goro; Awatani, Yuto; Isomi, Kazuhiko

no journal, , 

no abstracts in English

28 (Records 1-20 displayed on this page)