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Journal Articles

Environmental research on uranium at the Ningyo-Toge Environmental Engineering Center, JAEA

Sato, Kazuhiko; Yagi, Naoto; Nakagiri, Toshio

Proceedings of 27th International Conference on Nuclear Engineering (ICONE-27) (Internet), 6 Pages, 2019/05

no abstracts in English

Journal Articles

Development of cement based encapsulation for low radioactive liquid waste in Tokai Reprocessing Plant

Matsushima, Ryotatsu; Sato, Fuminori; Saito, Yasuo; Atarashi, Daiki*

Proceedings of 3rd International Symposium on Cement-based Materials for Nuclear Wastes (NUWCEM 2018) (USB Flash Drive), 4 Pages, 2018/10

At TRP, LWTF was constructed as a facility for processing low radioactive liquid waste and solid waste generated at TRP, and a cold test is been carrying out. In this facility, initially, nitrate waste liquid after separation of nuclides generated with treatment of low radioactive liquid waste was to be solidified by using borate. However, at present, it is necessary to decompose the nitrate in the liquid waste to reduce the environmental burden. For the reason, as a plan to replace the nitrate with the carbonate and to make it as a cement based encapsulation, we are studying for the introduction of the facility. Currently, as a cement solidification technology development for this liquid waste, we are studying the application of cement material based on blast furnace slag (BFS) as a main component. In this report, we show the results of the test conducted on the actual scale (200 L drum can scale).

Journal Articles

Vitrification technology for radioactive wastes

Amamoto, Ippei

Journal of the Society of Inorganic Materials, Japan, 24(391), p.393 - 401, 2017/11

Glass is a non-crystalline solid, as such, it is relatively easy to change its composition to control its characteristics. The borosilicate glass, which is produced by the addition of boron oxide into sodium-lime glass, possesses excellent heat-resistant properties and mechanical strength. It has a wide variety of uses. The borosilicate glass is applied as the vitrified medium for radioactive wastes to immobilize and stabilize them for long term. The glass form which is loaded with high-level radioactive waste is called the vitrified waste. This paper classified the radioactive waste and describes treatment and production methods of vitrified waste, its characteristics, disposal method and also introduces alternative vitrified medium.

Journal Articles

Recent activities in the field of nuclear waste management

Kitamura, Akira; Kirishima, Akira*

Journal of Nuclear Science and Technology, 52(3), p.448 - 450, 2015/03

 Times Cited Count:1 Percentile:11.57(Nuclear Science & Technology)

The Journal of Nuclear Science and Technology covers a variety of subjects in the field of nuclear waste management, which includes radioactive waste treatment, radioactive waste disposal and environment, decommissioning and dismantling. This summary introduces activities presented in recent years.

JAEA Reports

Survey of the geological characteristics on the Japanese Islands for disposal of RI and research institute waste

Hagiwara, Shigeru*; Sakamoto, Yoshiaki; Takebe, Shinichi; Ogawa, Hiromichi; Nakayama, Shinichi

JAERI-Review 2002-038, 107 Pages, 2002/12

JAERI-Review-2002-038.pdf:6.72MB

For the disposal of radioactive waste arising from radioactive utilization facilities and nuclear facilities, it is necessary to establish the disposal system in proportion to half-lives of radionuclides and radioactivity concentration in the waste. It is important to grasp the features of the earth scientific phenomena and geological structure of our country for the disposal system of radioactive waste. Then, for the porpose of the survey of the geological characteristics around the Japanese Islands whole neiborhood, the earth scientific phenomena at present, geological structure and geotectonic history were summarized on the basis of the existing literatures.

JAEA Reports

Evaluation of operatinal condition in LWTF; Tests using technical scale equipment

; Murata, Eiichi*; Sawahata, Yoshikazu*; Saito, Akira*

JNC-TN8430 2001-002, 43 Pages, 2001/02

JNC-TN8430-2001-002.pdf:1.98MB

Japan Nuclear Cycle Development Institute (JNC) is designing the Low level radioactive Waste Treatment Facility (LWTF) in the Tokai Reprocessing Plant (TRP). The low level liquid waste generated the TRP is separated salt (NaNO$$_{3}$$, etc) and radionuclide in liquid treatment process of LWTF. The process can get higher volume reduction than previous bituminization. Based on the engineering tests equal to the liquid treatment process of LWTF, the validity of operational condition in LWTF is evaluated. As the results, it is confirmed that all operational condition in the processes which is Iodine immobilization, Pre-filter filtration, Pre-treatment, Coprecipitation and Ultrafiltration are available.

JAEA Reports

ICONE-8 participation and investigation report of dry process in Argonne National Laboratory (ANL), USA

; Washiya, Tadahiro;

JNC-TN8420 2001-009, 48 Pages, 2000/04

JNC-TN8420-2001-009.pdf:0.58MB

ICONE(International Conference on Nuclear Engineering) is an international conference on nuclear chemical engineering held among the United States, Japan and Europe, and ICONE8 (the 8th time of the conference) was held at Baltimore, USA on April 2 to 6, 2000. The authors of this paper reported the latest information on the reprocessing technology in the following session of the conference and audited the panel discussion and the technical report of the dry reprocessing technology etc. in the conference. (1)Investigation of Safety Evaluation Method and Application to Tokai Reprocessing Plant (TRP) in session of Track-5 "Non-reactor Safety and Reliability" (Nakamura) (2)Structural Improvement on the continuous rotary dissolver in session of Track-9 "Spent Nuclear Fuel and Waste Processing" (Washiya) (3)Development of Evaporators Made of Ti-5% Ta Alloy and Zr - Endurance Test By Mock-Up unit" in session of Track-2 "Aging and Modeling of Component Aging, Including corrosion of Metals and Welds.. passivation, and passive films" (Takata) At the conference, about 650 people participated from the United States, Japan, France, Canada and others, about700 research announcements, 7 keynote lecture and 8 panel discussion were done, flourishing with many participants. Moreover, as the conference was held in the year of 2000, the evaluation of this century and the direction of the next century of nuclear energy were discussed. After the conference, authors visited Argonne National Laboratory (ANL-E, ANL-W) and exchanged information concerning dry process with researchers of ANL-E and ANL-W, visiting ANL facilities. It was very significant to be able to acquire the information on the dry process developed in ANL and realize the device scale and the development environment, etc. and acquire technical information in detail which would not be able to obtain by engineering data, exchanging information with ANL engineers directly. It is suggested to be very valuable that the ...

JAEA Reports

None

Otagaki, Takao*; *

JNC-TJ8420 2000-016, 427 Pages, 2000/03

JNC-TJ8420-2000-016.pdf:18.18MB

no abstracts in English

JAEA Reports

Technology assessment of partitioning process, I; Status of the partitioning technology

; Takizuka, Takakazu

JAERI-M 94-067, 108 Pages, 1994/03

JAERI-M-94-067.pdf:3.58MB

no abstracts in English

Journal Articles

Treatment of radioactive waste in institutes

Kosako, Toshiso*; *; *;

Kenkyu Bunya-niokeru housyasei Haikibutu No Toriatukai, 0, p.27 - 31, 1994/03

no abstracts in English

JAEA Reports

Journal Articles

Journal Articles

Recent Trend in Radioactive Waste Management in Japan

Genshiryoku Kogyo, 16(8), p.5 - 9, 1970/00

no abstracts in English

JAEA Reports

Oral presentation

Current status of research and development program for decommissioning of Fukushima Daiichi Nuclear Power Station by IRID, 5; Research and development on treatment and disposal of radioactive waste generated from Fukushima Daiichi Nuclear Power Station accident

Oi, Takao

no journal, , 

The methodology for development of the waste management strategy and the relation between the strategy and each research on the treatment and disposal of the radioactive waste generated from Fukushima Daiichi Nuclear Power Plant accident in the presentation will be introduced.

Oral presentation

Current situation of radionuclides analysis on Fukushima Daiichi Nuclear Power Station

Meguro, Yoshihiro; Kato, Jun; Kishimoto, Katsumi; Kameo, Yutaka; Ishimori, Kenichiro; Tanaka, Kiwamu; Shibata, Atsuhiro; Koma, Yoshikazu; Ashida, Takashi

no journal, , 

The authors are working in study for radioactive wastes generated in Fukushima Daiichi. Radioactive inventory estimation of wastes is important in the study for the processing and disposal of radioactive waste. And then so many real wastes have to be analyzed for their inventory evaluation. In addition to this waste analysis, there are several needs for analysis. For example a large volume of the contaminated water is being decontaminated, and operational status and ability of this system should be checked by analysis of the treated water. And also groundwater and sea water are analyzing to understand contaminated situation, to estimate a leakage position, and to confirm leakage prevention. In future fuel debris will be analyzed for its material accountancy. In this presentation, actual situation of analyses in Fukushima Daiichi will be explained, mainly focus on analyses for the inventory evaluation of the radioactive waste.

Oral presentation

Current status of secondary wastes of contaminated water treatment and effort for processing and disposal of the wastes

Meguro, Yoshihiro

no journal, , 

Research and development for the processing and disposal of all radioactive wastes that were generated or will be generated in Fukushima Daiichi Nuclear Power Station is promoted. Here characterization of the wastes, safety assessment of long-term storage of the waste, waste stream, conditioning of the waste using existing techniques, evaluation of effect of uncertainty in the waste information on the safety evaluation of waste disposal have been investigated.

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

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 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

26 (Records 1-20 displayed on this page)