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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).
Ito, Yoshiyuki; Matsushima, Ryotatsu; Sato, Fuminori
QST-M-8; QST Takasaki Annual Report 2016, P. 69, 2018/03
no abstracts in English
Nakayama, Takuya; Kawato, Yoshimi; Osugi, Takeshi; Shimazaki, Takejiro; Hanada, Keiji; Suzuki, Shinji; Sakakibara, Tetsuro; Nakazawa, Osamu; Meguro, Yoshihiro
JAEA-Technology 2014-046, 56 Pages, 2015/03
JAEA-Technology-2014-046.pdf:7.61MB
The combustible and flame-retardant radioactive wastes generated as a result of the research activities in Japan Atomic Energy Agency (JAEA) are incinerating to reduce their volume. The incinerated ash is planned to be solidified using cement for disposal. Since the properties of ashes generated in each institute of JAEA are varied with the type of incinerator and the wastes to be incinerated, it is necessary to do fundamental solidification tests in each institute to decide operating conditions of the planning cement solidification facility. It is important to standardize evaluating methods of cement and solidified waste because some characters depend on measuring method. This user's guide have been prepared how to decide the cement solidifying conditions of ash to design the cement solidification facility in JAEA. Requirements on the regulations of solidified radioactive waste have been examined and seven technical criteria, e.g. compressive strength, fluidity, have been selected as characters to be evaluated. Some empirical notes about selection of cement, admixtures, procedure on making a test piece, evaluation of expanding, compressive strength, solubility have been described. The strategy of tests and tips for finding optimized solidification condition has been summarized. Finally the example of optimized conditions satisfied the requirements and some problems to be solved have been described.
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
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.
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 = 36, 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.
Iriya, Keishiro*; Kubo, Hiroshi*; *; Mukai, Satoru*; Kitao, Hideo*; Ishihara, Yoshinao*; Neyama, Atsushi*
PNC TJ1449 96-001, 379 Pages, 1996/03
None
Iriya, Keishiro*; Fujiwara, Yasushi*; Motohashi, Kenichi*; Nakanishi, Masatoshi*
PNC TJ1449 93-002, 91 Pages, 1993/03
None
Bamba, Tsunetaka; Matsumoto, Junko; Muraoka, Susumu
Cement Concrete Research, 22, p.381 - 386, 1992/00
Times Cited Count：0 Percentile：0.1(Construction & Building Technology)no abstracts in English
JAERI-M 89-156, 61 Pages, 1989/10
no abstracts in English
JAERI-M 8392, 16 Pages, 1979/08
no abstracts in English
Hoken Butsuri, 14(3), p.197 - 201, 1979/00
no abstracts in English
Cs in the Crushed Samples; Wadachi, Yoshiki;
JAERI-M 6749, 16 Pages, 1976/10
no abstracts in English
; ; ; ; Wadachi, Yoshiki;
JAERI-M 6457, 11 Pages, 1976/03
no abstracts in English
; ;
JAERI-M 6364, 14 Pages, 1976/01
no abstracts in English
; ; ; Wadachi, Yoshiki
Nihon Genshiryoku Gakkai-Shi, 17(1), p.27 - 30, 1975/01
no abstracts in English
Cs from Solidified Cement Blocks; ; ;
JAERI-M 5779, 36 Pages, 1974/07
no abstracts in English
; *
Genshiryoku Kogyo, 20(1), p.25 - 32, 1974/01
no abstracts in English
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.
