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JAEA Reports

Development of waste management system, 1; Concept construction of the system

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.

JAEA Reports

Study on hazardous substances contained in radioactive waste

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.

JAEA Reports

Proposal of a Nuclear Cycle Research and Development Plan in Tokai Works -The Roadmap from LWR Cycle to FBR Cycle-

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.

Journal Articles

None

Kuroki, Ryoichiro; Suzuki, Satoshi*; *; ; ; Yasu, Takami

Donen Giho, (103), p.55 - 63, 1997/09

None

Oral presentation

Development of the waste management system, 1; Concept construction of the system

Kuroki, Ryoichiro; Nakata, Hisakazu; Yamamoto, Shuji; Takahashi, Kuniaki

no journal, , 

Various waste data are needed for quality assurance of low level waste packages which are generated and conditioned in JAEA, and as basic data for consideration of the disposal regulation, design of the disposal facility, and so on. Therefore, the system to manage the waste data from generation to disposal will be developed. Then the concept of this system was considered. At first, development policy was defined depend on the situation and problem of waste management in JAEA, and the target needs of this system were selected. Then concept of this system was constructed, and data items to be managed in this system were selected. This system consists of four function units, each analytical and management function for quality assurance and another needs. Both management units and both analytical units are developed as the application program and as the database, these units are constructed on the network of JAEA. And over 400 data items to be managed in this system were shown.

Oral presentation

Environmental measures in the atomic industry of Japan (including the waste treatment and conditioning technology)

Kuroki, Ryoichiro

no journal, , 

(1) Environmental measures in the atomic industry of Japan (eliminattion of radioactive materials and toxic substances, effluent management, etc), (2) Summary of treatment and disposal of radioactive waste, (3) Development of waste treatment technologies, etc.

Oral presentation

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.

Oral presentation

Research and development on preceding processing methods for contaminated water management waste at Fukushima Daiichi Nuclear Power Station, 1; Examination of Task on processing

Kato, Jun; Taniguchi, Takumi; Namiki, Masahiro*; Imaizumi, Ken*; Terasawa, Toshiharu*; Osugi, Takeshi; Sone, Tomoyuki; Nakazawa, Osamu; Kuroki, Ryoichiro; Koma, Yoshikazu

no journal, , 

Regarding solidification technologies with applied performance for radioactive waste processing, tasks for applicability evaluation of these technologies to contaminated water treatment secondary waste at Fukushima Daiichi Nuclear Power Station was extracted in FY2017. This report introduces the examination for the extracted tasks implemented in FY2018.

Oral presentation

Introduction of research and development regarding treatment technology for TEPCO's Fukushima Daiichi NPS accident waste

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.

Oral presentation

Research and development on preceding processing methods for contaminated water management waste at Fukushima Daiichi Nuclear Power Station, 6; Numerical simulation analysis of relationships between nuclide inventory and solidified body temperature

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.

Oral presentation

Research and development on preceding processing methods for contaminated water management waste at Fukushima Daiichi Nuclear Power Station, 4; Evaluation of dissolution behavior on solidified body of cement and Alkali Activated Material

Kaneda, Yoshihisa*; Haga, Kazuko*; Shibata, Masahito*; Kuranaga, Mebae*; Kikuchi, Michio*; Yamamoto, Takeshi*; Kato, Jun; Osugi, Takeshi; Kuroki, Ryoichiro

no journal, , 

Solidified cement and alkali activated materials was made, and used for dissolution test to obtain basic data of solidification on the waste caused by the contaminated water treatment at Fukushima Daiichi Nuclear Power Station.

Oral presentation

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.

Oral presentation

Research and development on preceding processing methods for contaminated water management waste at Fukushima Daiichi Nuclear Power Station, 2; Investigation of approach for selecting solidification techniques applied to contaminated water management waste

Furukawa, Shizue*; Koyama, Tadafumi*; Kikuchi, Michio*; Otsuka, Taku*; Yamamoto, Takeshi*; Imaizumi, Ken*; Osugi, Takeshi; Nakazawa, Osamu; Kuroki, Ryoichiro

no journal, , 

In order to evaluate the application to the solidification of the water treatment secondary waste generated from Fukushima Daiichi Nuclear Power Station, research concerning the approach of applicability evaluation was conducted for solidification technology of practical scale.

Oral presentation

Research and development on preceding processing methods for contaminated water management waste at Fukushima Daiichi Nuclear Power Station, 7; Numerical analysis of temperature rise of solidified waste by radiation applying various container shapes

Hiraki, Yoshihisa; Enomoto, Mayu*; Terasawa, Toshiharu*; Imaizumi, Ken*; Kato, Jun; Osugi, Takeshi; Sone, Tomoyuki; Kuroki, Ryoichiro

no journal, , 

Evaluate the maximum temperature of solidified body, when Secondary Waste Produced from Contaminated Water Treatment at Fukushima Daiichi NPP is solidified with cement etc. Simulate various container shapes, and analysis using the radiation transport code and the thermal analysis code was performed. The summary of the test and some of the obtained results are introduced.

Oral presentation

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.

Oral presentation

Research and development on preceding processing methods for contaminated water management waste at Fukushima Daiichi Nuclear Power Station, 8; Investigation of method for screening test of contaminated water management waste applied to solidification by cement and Alkali Activated Material

Taniguchi, Takumi; Namiki, Masahiro*; Osugi, Takeshi; Sone, Tomoyuki; Kuroki, Ryoichiro; Kikuchi, Michio*; Yamamoto, Takeshi*; Otsuka, Taku*; Kaneda, Yoshihisa*; Osawa, Norihisa*; et al.

no journal, , 

no abstracts in English

Oral presentation

Physical properties test for solidification strength and long-term stability of K-based alkali-activated materials

Kakuda, Ayaka; Osone, Osamu*; Hiraki, Yoshihisa; Osugi, Takeshi; Sone, Tomoyuki; Kuroki, Ryoichiro; Kudo, Isamu*; Elakneswaran, Y.*; Sato, Tsutomu*

no journal, , 

no abstracts in English

Oral presentation

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.

Oral presentation

Research and development on preceding processing methods for contaminated water management waste at Fukushima Daiichi Nuclear Power Station, 10; Characteristic evaluation of carbonate slurry-containing solidified body formed by cement or alkali activated material

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

no journal, , 

In order to obtain data to be used in the evaluation of the applicability of low temperature processing to carbonate slurry generated by contaminated water treatment at Fukushima Daiichi Nuclear Power Station, the basic properties of the solidified cement and alkali activated material blended simulated carbonated slurry were evaluated. An overview of the study and some of the results obtained are reported here.

Oral presentation

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.

39 (Records 1-20 displayed on this page)