X ray spectroscopy on atoms (J-PARC E03, E07 and future)

Yamamoto, Takeshi; Fujita, Manami; Gogami, Toshiyuki*; Harada, Takeshi*; Hayakawa, Shuhei*; Hosomi, Kenji; Ichikawa, Yudai; Ishikawa, Yuji*; Kamata, K.*; Kanauchi, H.*; et al.

EPJ Web of Conferences, 271, p.03001_1 - 03001_5, 2022/11

https://doi.org/10.1051/epjconf/202227103001

Gamma-ray spectroscopy of single -hypernuclei at J-PARC; Results and perspective

Koike, Takeshi*; Hasegawa, Shoichi; Hayakawa, Shuhei*; Hosomi, Kenji; Ichikawa, Yudai; Imai, Kenichi; Sako, Hiroyuki; Sato, Susumu; Sugimura, Hitoshi; Tamura, Hirokazu; et al.

AIP Conference Proceedings 2130, p.020011_1 - 020011_9, 2019/07

https://doi.org/10.1063/1.5118379

Application study on low alkaline cementitious materials for deep geological repository of high level radioactive wastes, 2; Organization of previous finding and understanding of material properties of low alkaline cement (Joint research)

Kobayashi, Yasushi; Yamada, Tsutomu; Naito, Morimasa; Yui, Mikazu; Nakayama, Masashi; Sato, Haruo; Nishida, Takahiro*; Hironaga, Michihiko*; Yamamoto, Takeshi*; Sugiyama, Daisuke*; et al.

JAEA-Research 2009-013, 70 Pages, 2009/06

JAEA-Research-2009-013.pdf:8.85MB

Cementitious materials will be used to ensure construction and operational safety and work efficiency in a deep geological repository. The low alkaline cement has been developed to reduce uncertainties due to hyper alkaline for the long-term safety performance of the repository system. Functions of cementitious material required in each phase of repository construction, operation and closure were summarized in a separate report entitled "Application Study on Low Alkaline Cementitious Materials for Deep Geological Repository of High Level Radioactive Wastes (Phase I) "In this report, properties of low alkaline cement/concrete which have been developed both at home and abroad, and recipes of the low alkaline concrete taken account of application to the repository component have been investigated. Fresh and hardened properties of the low alkaline cement are equivalent to the OPC and the low alkaline cement has an advantage over OPC in terms of leaching resistance. The HFSC developed by JAEA, which belongs to a pozzolanic type low alkaline cement will be able to apply to the shotcrete and the lining concrete by choosing an adequate recipe. Clarification of influences of the chemical composition of groundwater on leachate properties of the hydrates, examination of pH measurement of cement leachate, evaluation of corrosion behavior of rebar embedded in the HFSC concrete are raised as open questions for future activities.

Recovery of alkali salt by supercritical fluid leaching method using carbon dioxide

Watanabe, Takeshi*; Tsushima, Satoru*; Yamamoto, Ichiro*; Tomioka, Osamu; Meguro, Yoshihiro; Nakashima, Mikio; Wada, Ryutaro*; Nagase, Yoshiyuki*; Fukuzato, Ryuichi*

Proceedings of 2nd International Symposium on Supercritical Fluid Technology for Energy and Environment Applications (Super Green 2003), p.363 - 366, 2004/00

Recovery of salts by supercritical fluid leaching (SFL) method using carbon dioxide was experimentally studied. It was confirmed that LiCl was recovered with a mixed fluid of carbon dioxide and methanol, and KCl and SrCl were recovered with a mixed fluid of carbon dioxide, methanol and crown ether. The influence of crown ether for KCl and SrCl extraction were found to increase in the order of 15-crown-5 (15C5) 18-crown-6 (18C6) dicychlohexyl-18-crown-6 (DC18C6). It is expected that other salts can be recovered selectively with a mixed fluid of carbon dioxide, methanol and suitable crown ether.

Prediction of ambient dose equivalent rates within 80km radius of the Fukushima NPP

Kinase, Sakae; Murakami, Yuko; Takahashi, Tomoyuki*; Suzuki, Tadakazu*; Sugita, Takeshi*; Ando, Masaki; Mikami, Satoshi; Yamamoto, Hideaki; Saito, Kimiaki

no journal, , 

no abstracts in English

Research and development on preceding processing methods for contaminated water management waste at Fukushima Daiichi Nuclear Power Station, 5; Gamma-ray irradiation test on solidified body of cement and Alkali Activated Material

Taniguchi, Takumi; Imaizumi, Ken*; Namiki, Masahiro*; Osugi, Takeshi; Kuroki, Ryoichiro; Kikuchi, Michio*; Yamamoto, Takeshi*; Kaneda, Yoshihisa*; Haga, Kazuko*

no journal, , 

It is important to understand fundamental solidification characteristics of contaminated water management waste at Fukushima Daiichi Nuclear Power Station. The Solidified bodies are fabricated with cementitious material and Alkali Activated Material, and are irradiated with Gamma-ray.

Research and development on preceding processing methods for contaminated water management waste at Fukushima Daiichi Nuclear Power Station, 3; Outline of characteristics evaluation study on solidified body of cement and Alkali Activated Material

Kikuchi, Michio*; Yamamoto, Takeshi*; Otsuka, Taku*; Kawato, Takaya*; Kaneda, Yoshihisa*; Shibata, Masahito*; Haga, Kazuko*; Taniguchi, Takumi; Osugi, Takeshi; Kuroki, Ryoichiro

no journal, , 

Summary of the study which is for characterization of Solidified cement and alkali activated materials was carried out due to obtain the data available for applicability evaluation low-temperature solidification on the waste caused by the contaminated water treatment at Fukushima Daiichi Nuclear Power Station.

Research and development on preceding processing methods for contaminated water management waste at Fukushima Daiichi Nuclear Power Station, 13; Gamma-ray irradiation characteristics of solidified materials containing carbonate slurry

Kato, Jun; Imaizumi, Ken*; Osugi, Takeshi; Sone, Tomoyuki; Kuroki, Ryoichiro; Kikuchi, Michio*; Yamamoto, Takeshi*; Otsuka, Taku*; Kaneda, Yoshihisa*; Osawa, Norihisa*

no journal, , 

Solidified cement and Alkali Activated Materials (AAM) containing simulated carbonated slurry was prepared, and the amount of Hydrogen gas generation on gamma-ray irradiation was determined. The obtained data was compared with the data of solidified material without any content of waste, and the effect for Hydrogen gas generation with the material containing simulated carbonated slurry was evaluated.

Research and development on preceding processing methods for contaminated water management waste at Fukushima Daiichi Nuclear Power Station, 9; Synthesis of simulated carbonate slurry

Nakashio, Nobuyuki*; Kawasoe, Takahiro*; Aikawa, Kohei*; Kikuchi, Michio*; Yamamoto, Takeshi*; Kaneda, Yoshihisa*; Haga, Kazuko*; Osugi, Takeshi; Sone, Tomoyuki; Kuroki, Ryoichiro

no journal, , 

Simulated carbonate slurry was synthesized to obtain basic data for the low temperature processing of the waste generated from contaminated water treatment at Fukushima Daiichi Nuclear Power Station. An overview of the study and some of the results obtained are reported here.

Research and development on preceding processing methods for contaminated water management waste at Fukushima Daiichi Nuclear Power Station, 11; Dissolution test of solidified body of cement and Alkali Activated Material

Kaneda, Yoshihisa*; Haga, Kazuko*; Shibata, Masahito*; Osawa, Norihisa*; Kikuchi, Michio*; Yamamoto, Takeshi*; Kawato, Takaya*; Osugi, Takeshi; Sone, Tomoyuki; Kuroki, Ryoichiro

no journal, , 

Solidified cement and alkali activated material blending carbonated slurry were prepared and their dissolution tests were carried out in order to obtain basic data for the low temperature processing of the waste generated by contaminated water treatment at Fukushima Daiichi Nuclear Power Station. An overview of the study and some of the results obtained are reported here.