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Journal Articles

Thermal-hydraulics technological strategy roadmap 2017; An Approach for continuous safety improvement of LWRs

Itoi, Tatsuya*; Iwaki, Chikako*; Onuki, Akira*; Kito, Kazuaki*; Nakamura, Hideo; Nishida, Akemi; Nishi, Yoshihisa*

Nihon Genshiryoku Gakkai-Shi ATOMO$$Sigma$$, 60(4), p.221 - 225, 2018/04

no abstracts in English

Journal Articles

Japanese research activities for Fukushima-Daiichi decommissioning

Okamoto, Koji; Ogawa, Toru

Proceedings of 2016 EFCOG Nuclear & Facility Safety Workshop (Internet), 3 Pages, 2016/09

The decommissioning of the Fukushima-Daiichi Nuclear Power Plant has required and will continue to demand conducting many challenging activities, many of which do not have prior experience in the nuclear industry. International decommissioning knowledge and technology advances will be required to support the challenging work. The Collaborative Laboratories for Advanced Decommissioning Science (CLADS) was established by the Japan Atomic Energy Agency (JAEA) in April 2015. The main objectives of CLADS are the management, research and development for decommissioning at the Fukushima-Daiichi site. Not only is the coordination of research and development important to effective decommissioning, but also the management of research activities around the world. A status of the CLADS program will be provided. The CLADS central research office will be located at Tomioka Town, near the Fukushima site, in April 2017.

Journal Articles

Thermal-hydraulics technological strategy roadmap that improves safety of LWRs

Arai, Kenji*; Umezawa, Shigemitsu*; Oikawa, Hirohide*; Onuki, Akira*; Nakamura, Hideo; Nishi, Yoshihisa*; Fujii, Tadashi*

Nihon Genshiryoku Gakkai-Shi ATOMO$$Sigma$$, 58(3), p.161 - 166, 2016/03

no abstracts in English

JAEA Reports

Development of a cutting technique of core structural materials and fuel debris; Applicability test of the plasma jet cutting technique

Shoji, Tsugio; Fukui, Yasutaka; Ueda, Takiho

JAEA-Technology 2015-035, 70 Pages, 2016/01

JAEA-Technology-2015-035.pdf:8.07MB

The plasma jet cutting technology (Max output current is 250A) is developed for the dismantling of nuclear facilities in Oarai Research and Development Center. The plasma jet cutting technology is applicable to take out the debris. The plasma jet torch (Max output current is 600A) was produced for this application. This torch is available for the cutting of thick core internal materials in water. The ability of taking out debris and core internal material has been confirmed.

Oral presentation

Development of plasma heating technology for simulation of LWR severe accident behavior, 2; Outcomes of JFY2015

Abe, Yuta; Sato, Ikken; Nakagiri, Toshio; Nagae, Yuji; Ishimi, Akihiro

no journal, , 

no abstracts in English

Oral presentation

Visualization of the boron distribution in simulated melted core material by neutron energy resolving method

Kai, Tetsuya; Abe, Yuta; Matsumoto, Yoshihiro*; Parker, J. D.*; Shinohara, Takenao; Oishi, Yuji*; Nagae, Yuji; Sato, Ikken

no journal, , 

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