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Taniguchi, Takumi; Matsumoto, Saori; Hiraki, Yoshihisa; Sato, Junya; Fujita, Hideki*; Kaneda, Yoshihisa*; Kuroki, Ryoichiro; Osugi, Takeshi
JAEA-Review 2024-059, 20 Pages, 2025/03
JAEA-Review-2024-059.pdf:1.0MB
The basic performance required for solidifying waste into cement, such as fluidity before curing and strength after curing, is expected to be affected by the chemical effects of substances and components contained in the waste. The fluidity before curing and the strength properties after curing are greatly influenced by the curing speed of the cement. We investigated existing knowledge with a focus on chemical substances that affect the curing speed of cement. In this report, chemical substances that affect fluidity are broadly classified into inorganic substances such as (1) anion species, (2) metal elements such as heavy metals, (3) inorganic compounds as cement admixtures, and (4) organic compounds as cement admixtures. Based on the investigation, we actually added chemicals and measured the setting time. As a result, it was found that there are multiple mechanisms contributing to accelerated hardening. We investigated chemical substances that inhibit the curing reaction of cement, and were able to compile information to consider ingredients that are contraindicated in cement curing.
Kuroki, Ryoichiro; Ito, Fuminori*; Nakata, Hisakazu; Yamamoto, Shuji; Takahashi, Kuniaki
JAEA-Technology 2009-016, 124 Pages, 2009/06
JAEA-Technology-2009-016.pdf:3.8MB
The concept of "Waste Management System" which manages all the waste data from generation to disposal in Japan Atomic Energy Agency (JAEA) was studied. At first, development policy was defined on investigation results of the present state and problem of waste management in JAEA, and target information supplied by "Waste Management System" were extracted. Then over 400 data items to be managed in this system, system configuration and specific functions were shown as system concept. The waste data managed on this system are classified into two categories; for quality assurance of waste packages and for optimization study of waste conditioning and disposal and information service. This system consists of analytical part (i.e. program) and management part (i.e. database) for each data, then all these parts are constructed on network.
Kuroki, Ryoichiro; Takahashi, Kuniaki
JAEA-Research 2007-082, 215 Pages, 2008/01
JAEA-Research-2007-082.pdf:7.2MB
The environmental impact of hazardous materials and possibility of criticality were investigated to construct technical specification of radioactive waste packages. The contents and results are as following. (1) Concerning hazardous materials included in TRU waste, regulations on disposal of industrial wastes and on environmental preservation were investigated. (2) The assessment methods for environmental impact of hazardous materials included in radioactive waste in U.K, U.S.A. and France were investigated. (3) The upper limits of amounts of hazardous materials in waste packages to satisfy the environmental standard were calculated with mass transport assessment for some disposal concepts. (4) It was suggested from criticality analysis for waste packages in disposal facility that the occurrence of criticality was almost impossible under the realistic conditions.
Nakamura, Hirofumi; Abe, Tomiyuki; Kashimura, Takao; Nagai, Toshihisa; Maeda, Seiichiro; Yamaguchi, T.; Kuroki, Ryoichiro
JNC TN8440 2003-016, 39 Pages, 2003/07
JNC-TN8440-2003-016.pdf:0.79MB
The Generation-II Project Task Force Team has investigated a research and development plan on a future nuclear fuel cycle in Tokai works for about three months from December 19,2002. First we have discussed about the present condition of Japanese nuclear fuel cycle and have recognized it as the following. *The relation of the technology between the LWR-cycle and the FBR-cycle is not clear. *MOX Fuel Use in Light Water Reactors is important to establish technology of the FBR fuel cycle. *Radioactive waste disposal issue is urgent. Next we have proposed the three basic policies on R&D plan of nuclear fuel cycle in consideration of the F.S. on FBR-cycle. *Establishment and advancement of "the tough nuclear fuel cycle". *Early establishment of the FBR cycle technology to be able to supply energy stably for long-term. *Establishment of the radioactive waste treatment and disposal technology, and optimization of nuclear fuel cycle technology from the viewpoint of radioactive waste.And we have proposed the Japanese technical holder system to integrate all LWR and FBR cycle technology.
Kuroki, Ryoichiro; Suzuki, Satoshi*; ; ; ; Yasu, Takami
Donen Giho, (103), p.55 - 63, 1997/09
None
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.
Hiraki, Yoshihisa; Terasawa, Toshiharu*; Imaizumi, Ken*; Taniguchi, Takumi; Kato, Jun; Osugi, Takeshi; Sone, Tomoyuki; Nakazawa, Osamu; Kuroki, Ryoichiro
no journal, ,
The relationship between the amount of radionuclide to be solidified and the solidified body temperature was analyzed, when solidify contaminated water management waste at Fukushima Daiichi Nuclear Power Station with cement etc. at low temperature. The analysis code used the radiation transport code and the thermal analysis code. Thus, the limit value by radionuclide concentration during solidification process are evaluated. The summary of the test and some of the obtained results are introduced.
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.
Uruga, Kazuyoshi*; Furukawa, Shizue*; Koyama, Tadafumi*; Osugi, Takeshi; Sone, Tomoyuki; Kuroki, Ryoichiro
no journal, ,
no abstracts in English
Kobayashi, Yutaro*; Haga, Kazuko*; Kaneda, Yoshihisa*; Kuroda, Kazuma*; Sato, Tsutomu*; Osugi, Takeshi; Sone, Tomoyuki; Kuroki, Ryoichiro
no journal, ,
no abstracts in English
Kikuchi, Michio*; Furukawa, Shizue*; Koyama, Tadafumi*; Otsuka, Taku*; Yamamoto, Takeshi*; Imaizumi, Ken*; Osugi, Takeshi; Sone, Tomoyuki; Kuroki, Ryoichiro
no journal, ,
no abstracts in English
Hiraki, Yoshihisa; Saito, Toshimitsu*; Kakuda, Ayaka; Osugi, Takeshi; Sone, Tomoyuki; Kuroki, Ryoichiro; Kudo, Isamu*; Elakneswaran, Y.*; Sato, Tsutomu*
no journal, ,
no abstracts in English
Kakuda, Ayaka; Taniguchi, Takumi; Namiki, Masahiro*; Kikuchi, Michio*; Yamamoto, Takeshi*; Kaneda, Yoshihisa*; Osawa, Norihisa*; Osugi, Takeshi; Sone, Tomoyuki; Kuroki, Ryoichiro
no journal, ,
no abstracts in English
Kikuchi, Michio*; Yamamoto, Takeshi*; Otsuka, Taku*; Kawato, Takaya*; Kaneda, Yoshihisa*; Sakamoto, Ryo*; Haga, Kazuko*; Kakuda, Ayaka; Osugi, Takeshi; Sone, Tomoyuki; et al.
no journal, ,
no abstracts in English
Kato, Jun; Taniguchi, Takumi; Osugi, Takeshi; Nakazawa, Osamu; Sone, Tomoyuki; Kuroki, Ryoichiro
no journal, ,
Contaminated water treatment secondary wastes have diversity and have property without processing achievement so far. Tasks for applicability evaluation of these wastes were extracted concerning solidification technologies with applied achievement for radioactive waste processing by FY2017. This report introduces research and development for solving the extracted tasks.
Otsuka, Taku*; Kikuchi, Michio*; Yamamoto, Takeshi*; Kawato, Takaya*; Kurashige, Isao*; Kakuda, Ayaka; Osugi, Takeshi; Sone, Tomoyuki; Kuroki, Ryoichiro
no journal, ,
no abstracts in English
Takahashi, Yuta; Kakuda, Ayaka; Enomoto, Mayu*; Imaizumi, Ken*; Osugi, Takeshi; Sone, Tomoyuki; Kuroki, Ryoichiro
no journal, ,
no abstracts in English
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.
Koyama, Tadafumi*; Uruga, Kazuyoshi*; Furukawa, Shizue*; Vienna, J.*; Parruzot, B.*; Xiaonan, L.*; Osugi, Takeshi; Sone, Tomoyuki; Kuroki, Ryoichiro
no journal, ,
no abstracts in English
Kobayashi, Yutaro*; Haga, Kazuko*; Kaneda, Yoshihisa*; Sato, Tsutomu*; Kakuda, Ayaka; Osugi, Takeshi; Sone, Tomoyuki; Kuroki, Ryoichiro
no journal, ,
no abstracts in English
