JOPSS - Search Results

Journal Articles

New precise measurements of muonium hyperfine structure at J-PARC MUSE

Strasser, P.*; Abe, Mitsushi*; Aoki, Masaharu*; Choi, S.*; Fukao, Yoshinori*; Higashi, Yoshitaka*; Higuchi, Takashi*; Iinuma, Hiromi*; Ikedo, Yutaka*; Ishida, Katsuhiko*; et al.

EPJ Web of Conferences, 198, p.00003_1 - 00003_8, 2019/01

https://doi.org/10.1051/epjconf/201919800003

Times Cited Count：13 Percentile：98.48(Quantum Science & Technology)

Journal Articles

Report on activities related to fostering nuclear security culture in Tokai Reprocessing Facility

Kitao, Takahiko; Takeuchi, Yoshikatsu; Kimura, Takashi; Kojima, Junji; Shioya, Satoshi; Tasaki, Takashi; Nakamura, Hironobu

Nihon Kaku Busshitsu Kanri Gakkai Dai-38-Kai Nenji Taikai Rombunshu (Internet), 9 Pages, 2018/04

In order to ensure and strengthen nuclear security measures, an active cultivation of nuclear security culture implemented by both entire organization and individual persons is vitally essential. Tokai reprocessing facility has conducted various activities such as case study education and training, yearly posters and patrolling the site by upper-level management that all employees hold a deep rooted belief that there is a credible insider and outsider threat, and that nuclear security is important. These activities are conducted in order to establish the foundation of beliefs and attitudes of effective nuclear security culture based on the IAEA guideline. This report introduces our activities fostering nuclear security culture in Tokai reprocessing facility that the evaluation and the continuous improvement of bidirectional activities by both top-down from multiple management levels and bottom-up from individual employee, and our challenges need to be worked on for the future.

Journal Articles

Investigation of hydrogen gas generation by radiolysis for cement-solidified products of used adsorbents for water decontamination

Sato, Junya; Kikuchi, Hiroshi*; Kato, Jun; Sakakibara, Tetsuro; Matsushima, Ryotatsu; Sato, Fuminori; Kojima, Junji; Nakazawa, Osamu

QST-M-8; QST Takasaki Annual Report 2016, P. 62, 2018/03

https://repo.qst.go.jp/records/73811

no abstracts in English

Journal Articles

Hydrogen generation from cement solidified sample loading carbonate by gamma irradiation

Ito, Yoshiyuki; Sato, Fuminori; Kojima, Junji

QST-M-2; QST Takasaki Annual Report 2015, P. 89, 2017/03

https://repo.qst.go.jp/records/73804

no abstracts in English

Oral presentation

Development of treatment for low radioactive effluent in Tokai Reprocessing Plant, 11; Development plan and outline of cement based encapsulation

Sato, Fuminori; Horiguchi, Kenichi; Yamashita, Masaaki; Kojima, Junji

no journal, ,

no abstracts in English

Oral presentation

Basic study of the development of adsorptive separation technique for nuclear species in treated water using the silica-supported amphoteric ion exchanger

Komada, Ryo*; Yoshikawa, Yuta*; Arai, Tsuyoshi*; Sato, Fuminori; Kojima, Junji

no journal, ,

no abstracts in English

Oral presentation

Nuclear security measures at nuclear fuel facilities, 1; Trust worthiness program for insider mitigation method

Yamada, Hiroyuki; Kono, Soma; Tasaki, Takashi; Kojima, Junji; Kitao, Takahiko; Nakamura, Hironobu

no journal, ,

no abstracts in English

Oral presentation

Study on the performance of nuclides contamination in the iron phosphate glass

Mori, Masahiro*; Arai, Tsuyoshi*; Chaki, Takahito*; Sato, Fuminori; Kojima, Junji

no journal, ,

no abstracts in English

Oral presentation

Study on the composition and nuclide leaching behavior of the iron phosphate glass for Immobilization of low level radioactive waste

Chaki, Takahito*; Arai, Tsuyoshi*; Ishii, Kenji*; Sato, Fuminori; Kojima, Junji

no journal, ,

no abstracts in English

Oral presentation

Development of treatment for low radioactive effluent in Tokai Reprocessing Plant, 13; Full-scale experiment of cement based encapsulation

Yamashita, Masaaki; Sato, Fuminori; Horiguchi, Kenichi; Kojima, Junji; Sakai, Etsuo*; Atarashi, Daiki*; Kadota, Hirofumi*

no journal, ,

no abstracts in English

Oral presentation

Development for analysis method of trace elements in low-level radioactive liquid waste of reprocessing plant using iminodiacetic acid resin

Matsushima, Ryotatsu; Ito, Yoshiyuki; Kojima, Junji; Masuzawa, Shun*; Arai, Tsuyoshi*

no journal, ,

no abstracts in English

Oral presentation

Study on inorganic adsorbents for cesium and strontium removal from low level liquid wastes by reprocessing

Ito, Yoshiyuki; Kojima, Junji

no journal, ,

no abstracts in English

Oral presentation

Basic research programs for the next generation vitrification technology, 27; A Basic research on the applicability of iron phosphate glass for low-level radioactive waste; Viscosimetry of glass melt

Sato, Fuminori; Ishii, Kenji*; Kojima, Junji; Arai, Tsuyoshi*

no journal, ,

no abstracts in English

Oral presentation

Development of treatment for low radioactive effluent in Tokai Reprocessing Plant, 15 Study of cement based encapsulation in full-scale mixing

Matsushima, Ryotatsu; Sato, Fuminori; Horiguchi, Kenichi; Kojima, Junji; Yamashita, Masaaki*; Sakai, Etsuo*; Atarashi, Daiki*

no journal, ,

no abstracts in English

Oral presentation

Study of hydrogen generation from cement solidified products loading low radioactive liquid waste at Tokai reprocessing plant

Ito, Yoshiyuki; Matsushima, Ryotatsu; Sato, Fuminori; Kojima, Junji

no journal, ,

no abstracts in English

Oral presentation

Effect of retardants addition of the low-level radioactive liquid waste solidification using Mg cement

Yamanaka, Taiki*; Arai, Tsuyoshi*; Sato, Fuminori; Kojima, Junji

no journal, ,

no abstracts in English

Oral presentation

Development of treatment for low radioactive effluent in Tokai Reprocessing Plant 12; Small-scale experiment of cement based encapsulation

Horiguchi, Kenichi; Sato, Fuminori; Yamashita, Masaaki; Kojima, Junji; Kadota, Hirofumi*; Atarashi, Daiki*; Sakai, Etsuo*

no journal, ,

A large amount of nitrate in effluent occurring from Tokai reprocessing plant might cause environmental pollution. The effluent is planning to be encapsulated by cement after treated in the nitrate ion decomposition process. In this presentation, we will report the results of the small scale tests for cement solidification technology development of effluent containing a sodium carbonate.

Oral presentation

Investigation of hydrogen gas generation by -ray irradiation for cement-solidified products of used adsorbents for water decontamination

Sato, Junya; Kikuchi, Hiroshi*; Kato, Jun; Sakakibara, Tetsuro; Matsushima, Ryotatsu; Sato, Fuminori; Kojima, Junji; Nakazawa, Osamu

no journal, ,

no abstracts in English

Oral presentation

Basic study of the development of adsorptive separation technique for nuclear species from reactor core cooling water using the silica-supported amphoteric ion exchanger

Komada, Ryo*; Yabe, Yuki*; Arai, Tsuyoshi*; Sato, Fuminori; Kojima, Junji

no journal, ,

no abstracts in English

Oral presentation

Study on the leaching behavior of Na and volume reduction of low radioactive liquid waste

Chaki, Takahito*; Arai, Tsuyoshi*; Ishii, Kenji*; Sato, Fuminori; Kojima, Junji

no journal, ,

no abstracts in English

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New precise measurements of muonium hyperfine structure at J-PARC MUSE

Report on activities related to fostering nuclear security culture in Tokai Reprocessing Facility

Investigation of hydrogen gas generation by radiolysis for cement-solidified products of used adsorbents for water decontamination

Hydrogen generation from cement solidified sample loading carbonate by gamma irradiation

Development of treatment for low radioactive effluent in Tokai Reprocessing Plant, 11; Development plan and outline of cement based encapsulation

Basic study of the development of adsorptive separation technique for nuclear species in treated water using the silica-supported amphoteric ion exchanger

Nuclear security measures at nuclear fuel facilities, 1; Trust worthiness program for insider mitigation method

Study on the performance of nuclides contamination in the iron phosphate glass

Study on the composition and nuclide leaching behavior of the iron phosphate glass for Immobilization of low level radioactive waste

Development of treatment for low radioactive effluent in Tokai Reprocessing Plant, 13; Full-scale experiment of cement based encapsulation

Development for analysis method of trace elements in low-level radioactive liquid waste of reprocessing plant using iminodiacetic acid resin

Study on inorganic adsorbents for cesium and strontium removal from low level liquid wastes by reprocessing

Basic research programs for the next generation vitrification technology, 27; A Basic research on the applicability of iron phosphate glass for low-level radioactive waste; Viscosimetry of glass melt

Development of treatment for low radioactive effluent in Tokai Reprocessing Plant, 15 Study of cement based encapsulation in full-scale mixing

Study of hydrogen generation from cement solidified products loading low radioactive liquid waste at Tokai reprocessing plant

Effect of retardants addition of the low-level radioactive liquid waste solidification using Mg cement

Development of treatment for low radioactive effluent in Tokai Reprocessing Plant 12; Small-scale experiment of cement based encapsulation

Investigation of hydrogen gas generation by -ray irradiation for cement-solidified products of used adsorbents for water decontamination

Basic study of the development of adsorptive separation technique for nuclear species from reactor core cooling water using the silica-supported amphoteric ion exchanger

Study on the leaching behavior of Na and volume reduction of low radioactive liquid waste