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Journal Articles

The Survey for the integrity of containers for secondary wastes generated from contaminated water treatment

Iida, Yoshihisa; Nakadoi, Yasumasa; Yamaguchi, Tetsuji

Genshiryoku Bakkuendo Kenkyu (CD-ROM), 24(1), p.53 - 64, 2017/06

The information on the contaminated water treatment in Fukushima Daiichi Nuclear Power Station announced by Tokyo Electric Power Co., Inc. (TEPCO) were summarized in terms of the management of the secondary wastes, for the purpose of accumulating technical knowledge for long-term storage of the wastes. Concerns for the long-term soundness of waste storage containers were pointed out as follows, corrosion of stainless steel containers exposed to radiation in the presence of chloride ions, corrosion of stainless steel containers under acidic conditions or in the presence of activated carbon, and radiation degradation of the high-performance container (HIC) in which slurry was stored.

Journal Articles

Radioactive wastes generated from JAERI partitioning-transmutation cycle system

Nakayama, Shinichi; Morita, Yasuji; Nishihara, Kenji

Proceedings of International Conference on Back-End of the Fuel Cycle: From Research to Solutions (GLOBAL 2001) (CD-ROM), 6 Pages, 2001/09

Production of lower-level radioactive wastes, as well as the reduction in radioactivity of HLW, is an important performance indicator in assessing the viability of a partitioning-transmutation system. We have begun to identify the chemical compositions and to quantify the amounts of radioactive wastes that may be generated by JAERI's processes. Long-lived radionuclides such as $$^{14}$$C and $$^{59}$$Ni and spallation products of Pb-Bi coolants such as $$^{210}$$Po (10$$^{18}$$ Bq/yr) are added to the existing inventory of these nuclides that are generated in the current fuel cycle. Spent salts of KCl-LiCl, which is not generated from the current fuel cycle, will be introduced as a waste.

Journal Articles

Radioactive wastes generated from JAERI partitioning-transmutation cycle system

Nakayama, Shinichi; Morita, Yasuji; Nishihara, Kenji

Proceedings of International Conference on Back-End of the Fuel Cycle: From Research to Solutions (GLOBAL 2001) (CD-ROM), 6 Pages, 2001/00

no abstracts in English

Journal Articles

Radioactive wastes generated from double-strata nuclear fuel cycle for partitioning and transmutation

Nakayama, Shinichi; Morita, Yasuji; Nishihara, Kenji

KURRI-KR-57, p.55 - 62, 2000/11

no abstracts in English

JAEA Reports

None

*; *

JNC TJ8420 2000-013, 96 Pages, 2000/03

JNC-TJ8420-2000-013.pdf:6.04MB

no abstracts in English

Journal Articles

Wet partitioning and waste treatment

Morita, Yasuji; Kubota, Masumitsu

Hoshasei Haikibutsu Kenkyu, 2(1-2), p.75 - 83, 1996/02

no abstracts in English

Oral presentation

Oral presentation

Fundamental study of conditioning of wastes generated from several contaminated water treatment devices in Fukushima Daiichi Nuclear Power Station

Meguro, Yoshihiro; Sato, Junya; Kato, Jun; Nakagawa, Akinori; Koma, Yoshikazu; Ashida, Takashi

no journal, , 

A large quantity of contaminated water is accumulated in nuclear reactor buildings in Fukushima Daiichi Nuclear Power Station. Because various radionuclides are dissolved in the accumulated water, several decontamination devices based on deposition and adsorption are used for the decontamination. Therefore, several sludge and used adsorption materials are generated. These most are different from wastes caused by the operation of commercial nuclear power stations so far in properties, and these have not been disposed of commercially. As then feasibility of conventional solidification techniques to the wastes should be investigated prior to selection of solidification technique of the wastes. In this study as a first step of feasibility study, three types of sludge and three absorbents were solidified using cement materials and solidification behavior and properties of solidified material were investigated, and then feasibility of cementation to these wastes was evaluated.

Oral presentation

Characterization of secondary waste generated by Fukushima Daiichi Nuclear Power Station accident, 3; Analysis of slurry generated from multi-nuclide removal equipment

Fukuda, Yuhei; Suganuma, Takashi; Hinai, Hiroshi; Ikeda, Akira*; Obata, Masamichi*; Shibata, Atsuhiro; Nomura, Kazunori

no journal, , 

no abstracts in English

Oral presentation

Encapsulation study of secondary waste stream generated from treatment of contaminated water using the Geopolymer, 1; Encapsulation study of imitation sludge

Onozaki, Kimihiro*; Sato, Junya; Suzuki, Shinji*; Kato, Jun; Sakakibara, Tetsuro; Nakazawa, Osamu; Meguro, Yoshihiro; Mikami, Hisashi*; Platzka, M.*; Blazsekova, M.*

no journal, , 

no abstracts in English

Oral presentation

Study of pelletizing and sintering technologies of secondary wastes produced from contaminated water treatment, 1; Overview of the wastes and the sintering technology

Sato, Junya; Suzuki, Shinji*; Kato, Jun; Sakakibara, Tetsuro; Nakazawa, Osamu; Meguro, Yoshihiro; Ueda, Hiroshi*; Kurosaki, Fumio*; Yoneyama, Takashi*; Matsukura, Minoru*; et al.

no journal, , 

no abstracts in English

Oral presentation

Characterization of secondary waste generated by Fukushima Daiichi Nuclear Power Station accident, 4; Characteristics comparison of the existing and additional multiple radio-nuclides removal system slurry

Fukuda, Yuhei; Hinai, Hiroshi; Shibata, Atsuhiro; Nomura, Kazunori; Ikeda, Akira*; Obata, Masamichi*; Ichikawa, Masashi*; Takahashi, Ryota*; Hirayama, Fumio*

no journal, , 

no abstracts in English

Oral presentation

Characterization of secondary waste generated by Fukushima Daiichi Nuclear Power Station accident, 5; Analysis of carbonate slurry sampled from high integrity container

Fukuda, Yuhei; Arai, Yoichi; Hinai, Hiroshi; Nomura, Kazunori; Ikeda, Akira*; Obata, Masamichi*; Ichikawa, Masashi*; Takahashi, Ryota*; Hirayama, Fumio*

no journal, , 

no abstracts in English

Oral presentation

Development of solidification techniques with minimized water content for safe storage and disposal of secondary radioactive aqueous wastes in Fukushima

Meguro, Yoshihiro

no journal, , 

From contaminated water treatment systems at Fukushima Daiichi Nuclear Power Station, various radioactive wastes have been generated and stored. Especially, concentrated waste liquid, iron hydroxide slurry and carbonate slurry contain high concentration of strontium-90 and a large amount of water and sea water components. Therefore, when these wastes are stored for a long period, the risk of leakage of radioactive waste due to corrosion of storage containers and burning of hydrogen gas generated by radiolysis increases. In this research, we are developing technology to solidify these wastes using phosphate solidification materials. We are trying suppressing the generation of hydrogen gas by performing heat dehydration at the time of curing of the solidified material and to fix Sr and seawater component by making poorly water-soluble stable compounds.

Oral presentation

A Decontamination characteristic of the metal surface with uranium hexafluoride, 1; Basic test used simulation sample

Nakayama, Takuya; Nomura, Mitsuo; Mita, Yutaka; Sugitsue, Noritake; Yonekawa, Hitoshi*; Bunbai, Misako*; Yaita, Yumi*; Murata, Eiichi*; Hosaka, Katsumi*

no journal, , 

The metal surface exposed to uranium hexafluoride corrodes covering radioactive materials. We studied reasonably decontamination method. In this test, decontamination characteristics using water, diluted acid, functional electrolyzed water were evaluated using a simulated sample. As a result, we found that the oxidation-reduction potential of functional electrolyzed water affects decontamination performance.

Oral presentation

A Decontamination characteristic of the metal surface with uranium hexafluoride, 3; Evaluation of rational for decontamination technique

Nakayama, Takuya; Nomura, Mitsuo; Mita, Yutaka; Sugitsue, Noritake; Yonekawa, Hitoshi*; Bunbai, Misako*; Yaita, Yumi*; Murata, Eiichi*; Hosaka, Katsumi*

no journal, , 

For metal exposed to uranium hexafluoride, as a study of a method of reasonably decontaminating radioactive substances attached to a corrosion layer and a base material generated after opening to the atmosphere, removal using a simulated sample and an actual sample Based on the dyeing test results, evaluation of decontamination efficiency, secondary waste generation amount, etc. was carried out. As a result, it was confirmed that acidic functional water decontamination is totally superior to other dilution decontamination.

Oral presentation

A Decontamination characteristic of the metal surface with uranium hexafluoride, 2; Basic test used actual sample

Nakayama, Takuya; Nomura, Mitsuo; Mita, Yutaka; Sugitsue, Noritake; Yonekawa, Hitoshi*; Bunbai, Misako*; Yaita, Yumi*; Murata, Eiichi*; Hosaka, Katsumi*

no journal, , 

no abstracts in English

Oral presentation

Characterization of secondary waste generated by Fukushima Daiichi Nuclear Power Station accident, 7; Radiochemical analysis of sludge generated from decontamination device

Hinai, Hiroshi; Sato, Daisuke; Myodo, Masato; Koma, Yoshikazu; Shibata, Atsuhiro; Nomura, Kazunori

no journal, , 

no abstracts in English

Oral presentation

Characterization of secondary waste generated by Fukushima Daiichi Nuclear Power Station accident, 6; Analysis for characterization of sludge generated from decontamination device

Sato, Daisuke; Hinai, Hiroshi; Myodo, Masato; Koma, Yoshikazu; Shibata, Atsuhiro; Nomura, Kazunori

no journal, , 

no abstracts in English

40 (Records 1-20 displayed on this page)