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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).

JAEA Reports

The 4th technological meeting of Tokai Reprocessing Plant

; Maki, Akira; ; ; ; ; Fukuda, Kazuhito

JNC TN8410 2001-023, 188 Pages, 2001/11

JNC-TN8410-2001-023.pdf:30.98MB

"The 4th technological meeting of Tokai Reprocessing Plant (TRP)" was held in JNFL Rokkasyo site on octorber 11$$^{th}$$, 2001. The report contains the proceedings, transparancies and questionnaires of themeetin. This time, we reported about "Maintenance and repair results of Tokai Reprocessing Plant" based on technology and knowledge accumulated in Tokai Reprocessing Plant.

Journal Articles

Penetrant testing

Ooka, Norikazu; Ishii, Toshimitsu

Keikinzoku Yosetsu, 37(1), p.17 - 24, 1999/00

no abstracts in English

JAEA Reports

Historical overview on the development of the reprocessing technology in China

Tachimori, Shoichi

JAERI-Review 97-018, 37 Pages, 1998/01

JAERI-Review-97-018.pdf:2.05MB

no abstracts in English

Journal Articles

Beryllium neutron irradiation study in the Japan Materials Testing Reactor

Ishitsuka, Etsuo; Kawamura, Hiroshi

Fusion Engineering and Design, 41, p.195 - 200, 1998/00

 Times Cited Count:2 Percentile:24.47(Nuclear Science & Technology)

no abstracts in English

JAEA Reports

None

PNC TN8410 96-284, 245 Pages, 1996/03

PNC-TN8410-96-284.pdf:6.22MB

None

JAEA Reports

None

Ouchi, Jin; ; Kawamura, Kazuhiro

PNC TN8440 95-044, 148 Pages, 1995/10

PNC-TN8440-95-044.pdf:6.06MB

None

Journal Articles

Treatment program for liquid waste in JAERI's reprocessing test facility

Okane, Shogo; Miyajima, Kazutoshi; Takahashi, Hideki;

The 3rd JSME/ASME Joint Int. Conf. on Nuclear Engineering (ICONE),Vol. 4, 0, p.1905 - 1908, 1995/00

no abstracts in English

JAEA Reports

None

; ; Miyazaki, Hitoshi; ; Tanimoto, Kenichi; Terunuma, Seiichi

PNC TN9420 95-011, 13 Pages, 1994/10

PNC-TN9420-95-011.pdf:8.44MB

None

JAEA Reports

None

; Nakano, Tomoyuki; Miyazaki, Hitoshi;

PNC TN9420 94-015, 80 Pages, 1994/07

PNC-TN9420-94-015.pdf:2.92MB

None

JAEA Reports

None

; Kobayashi, Hiroaki; Masaki, Toshio; ; Kawamura, Kazuhiro; ;

PNC TN8440 94-028, 173 Pages, 1994/06

None

JAEA Reports

None

; Miyazaki, Hitoshi; ; Tanimoto, Kenichi; Terunuma, Seiichi

PNC TN9420 94-010, 103 Pages, 1994/04

PNC-TN9420-94-010.pdf:2.89MB

None

JAEA Reports

None

PNC TN9080 93-001, 25 Pages, 1992/12

PNC-TN9080-93-001.pdf:0.7MB

None

JAEA Reports

High radioactive $$alpha$$-$$gamma$$ solid Waste treatment facilities Conceptual design study

; Seki, Sadao*;

PNC TJ9409 91-001, 164 Pages, 1991/02

PNC-TJ9409-91-001.pdf:4.41MB

This report describes the result of conceptual design study concerned with "High Radioactive $$alpha$$-$$gamma$$ Solid Waste Treatment Facilities, "which will be planed for the purpose of volume reduction and stabilization of High Radioactive $$alpha$$-$$gamma$$ solid wastes generated and stocked in the O-arai Engineering Center of PNC. In this conceptual design study the basic process of the facilities, which are sufficient to treat each waste and develop technologies, are clarified. This report consist with: (1)Clarification of waste to be treated. (2)Study on the treatment technology and process. (3)Conceptual design of facilities and equipment. (4)Estimation of construction cost and schedule.

Oral presentation

Development of nuclear fuel cycle and fast reactor fuel reprocessing technology

Kofuji, Hirohide

no journal, , 

no abstracts in English

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

Oral presentation

Development of treatment for low radioactive effluent in Tokai Reprocessing Plant, 15 Study of cement based encapsulation in full-scale mixing

Matsushima, Ryotatsu; Sato, Fuminori; Horiguchi, Kenichi; Kojima, Junji; Yamashita, Masaaki*; Sakai, Etsuo*; Atarashi, Daiki*

no journal, , 

no abstracts in English

Oral presentation

Summary of the SmART cycle project of MA-MOX fuel which had extracted from Joyo spent fuel

Koizumi, Tsutomu

no journal, , 

no abstracts in English

Oral presentation

Current status of advanced reprocessing technology in JAEA

Takeuchi, Masayuki

no journal, , 

no abstracts in English

29 (Records 1-20 displayed on this page)