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Search Results: Records 1-14 displayed on this page of 14
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Journal Articles

Study on hydrogen generation from cement solidified products loading low-radioactive liquid wastes at Tokai Reprocessing Plant

Ito, Yoshiyuki; Matsushima, Ryotatsu; Sato, Fuminori

QST-M-8; QST Takasaki Annual Report 2016, P. 69, 2018/03

https://repo.qst.go.jp/records/73811

no abstracts in English

JAEA Reports

Study on microbial transport and adsorption behavior on engineering barrier for geological disposal of radioactive wastes

Fukunaga, Sakae*; Yokoyama, Hidekazu*; Arai, Kazuhiro*; Asano, Hidekazu*; Senjyu, Takafumi*; Kudo, Akira*

JNC TJ8400 2000-030, 54 Pages, 2000/02

JNC-TJ8400-2000-030.pdf:1.69MB

It is easy to assume from the past data that microbial transport do not find at 100%-sodium bentonite. Microbial transport do not find at 100%-calcium bentonite too. There are no effects to distribution ration (Kd) of Neptunium (Np) and Plutonium (Pu) with bentonite by sterilizing on low Eh condition (Eh= -500mv). Kd values of Np and Pu show behavior, which are increasing on the hard acidic and alkali conditions. Especially, Kd values of Pu shows one of Kd value is about 100 ml/g on pH=3$$sim$$6, but the other of Kd value is about 400,000 ml/g on pH=13. Precipitating plutonium hydrates occurred the large Kd value on alkali condition.

JAEA Reports

Study on microbial transport and adsorption behavior on engineering barrier for geological disposal of radioactive wastes

Fukunaga, Sakae*; Yokoyama, Hidekazu*; Arai, Kazuhiro*; Asano, Hidekazu*; Senjyu, Takafumi*; Kudo, Akira*

JNC TJ8400 2000-029, 36 Pages, 2000/02

JNC-TJ8400-2000-029.pdf:1.28MB

It is easy to assume from the past data that microbial transport do not find at 100%-sodium bentonite. Microbial transport do not find at 100%-calcium bentonite too. There are no effects to distribution ration (Kd) of Neptunium (Np) and Plutonium (Pu) with bentonite by sterilizing on low Eh condition (Eh = -500mv). Kd values of Np and Pu show behavior, which are increasing on the hard acidic and alkali conditions. Especially, Kd values of Pu shows one of Kd value is about 100 ml/g on pH = 3$$sim$$6, but the other of Kd value is about 400,000 ml/g on pH = 13. Precipitating plutonium hydrates occurred the large Kd value on alkali condition.

Journal Articles

Leaching behavior of carbon-14 contained in portland cement

Bamba, Tsunetaka; Matsumoto, Junko; Muraoka, Susumu

Cement Concrete Research, 22, p.381 - 386, 1992/00

https://doi.org/10.1016/0008-8846(92)90079-B
 Times Cited Count：0 Percentile：0.1(Construction & Building Technology)

no abstracts in English

JAEA Reports

Analysis of water movement and radionuclide migration in the backfill soil as an engineered barrier

JAERI-M 89-156, 61 Pages, 1989/10

JAERI-M-89-156.pdf:1.54MB

no abstracts in English

JAEA Reports

Study on the Inspection of Drum-Filled Cement Monolithic Solids of Radioactive Liquid Wastes for Sea Dumping; Non Destructive Ultrasonic Wave Velocing Test

JAERI-M 8392, 16 Pages, 1979/08

JAERI-M-8392.pdf:0.7MB

no abstracts in English

Journal Articles

Recovery and investigation of radioactive wastes disposed of in deepsea by USEPA

Hoken Butsuri, 14(3), p.197 - 201, 1979/00

https://doi.org/10.5453/jhps.14.197

no abstracts in English

JAEA Reports

Safety Evaluation of the Radioactive Waste-Cement Composites, 4; Leaching Behavior of $$^{1}$$$$^{3}$$$$^{7}$$Cs in the Crushed Samples

; Wadachi, Yoshiki;

JAERI-M 6749, 16 Pages, 1976/10

JAERI-M-6749.pdf:0.34MB

no abstracts in English

JAEA Reports

Safety Assessment of the Radioactive Waste-Cement Composites,3; Effect of the Geometry of Specimen on the Leachability

; ; ; ; Wadachi, Yoshiki;

JAERI-M 6457, 11 Pages, 1976/03

JAERI-M-6457.pdf:0.51MB

no abstracts in English

Journal Articles

The latest developments in salidification of radwaste

; *

Genshiryoku Kogyo, 20(1), p.25 - 32, 1974/01

http://ci.nii.ac.jp/naid/40017723218

no abstracts in English

Oral presentation

Study of hydrogen generation from cement solidified products loading low radioactive liquid waste at Tokai reprocessing plant

Ito, Yoshiyuki; Matsushima, Ryotatsu; Sato, Fuminori; Kojima, Junji

no journal, , 

no abstracts in English

Oral presentation

Development of treatment for low radioactive effluent in Tokai Reprocessing Plant, 16; Study on hydrogen generation from cement solidified products

Ito, Yoshiyuki; Matsushima, Ryotatsu; Sato, Fuminori; Saito, Yasuo

no journal, , 

no abstracts in English

Oral presentation

Development of treatment for low radioactive effluent in Tokai Reprocessing Plant, 20; Practical study on hydrogen generation from cement solidified products

Sato, Fuminori; Matsushima, Ryotatsu; Ito, Yoshiyuki; Saito, Yasuo

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, 40; Study of Leaching Test Method for Disposal Environments

Takahashi, Yuta; Taniguchi, Takumi; Kuroki, Ryoichiro; Osugi, Takeshi

no journal, , 

no abstracts in English

14 (Records 1-14 displayed on this page)
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