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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).
Shimizu, Daisuke*; Tsukada, Shinya*; Matsuura, Masato*; Sakamoto, Junya*; Kojima, Seiji*; Namikawa, Kazumichi*; Mizuki, Junichiro; Owada, Kenji
Physical Review B, 92(17), p.174121_1 - 174121_5, 2015/11
Times Cited Count:13 Percentile:50.04(Materials Science, Multidisciplinary)The phase diagram and the relationship between the crystal coherence length and electrical response of Pb[(MgNb)Ti]O (PMN-xPT) near the morphotropic phase boundary (MPB) have been precisely investigated using a single crystal with a Ti composition gradient by synchrotron X-ray diffraction and inelastic light scattering at room temperature. The crystal has two boundaries at Ti compositions of 29.0 mol% and 34.7 mol% which correspond to the phase boundaries between the monoclinic B (MB) and C (MC) phases and between the MC and tetragonal (T) phases, respectively. It is shown that there is a strong negative correlation between the electrical response and the crystal coherence length at the sub-m scale. The results are explained by the size effects of domains near the MPB.
Nakamichi, Masaru; Kim, Jae-Hwan; Munakata, Kenzo*; Shibayama, Tamaki*; Miyamoto, Mitsutaka*
Journal of Nuclear Materials, 442(1-3), p.S465 - S471, 2013/11
Times Cited Count:11 Percentile:64.2(Materials Science, Multidisciplinary)Kobayashi, Nobuo*; Sasaki, Shinichiro*; Tasaki, Keisuke*; Nakatsuka, Akira*; Nozawa, Shigeki; Hase, Yoshihiro; Narumi, Issei
JAEA-Review 2010-065, JAEA Takasaki Annual Report 2009, P. 67, 2011/01
Kobayashi, Nobuo*; Kano, Sayaka*; Sasaki, Shinichiro*; Tasaki, Keisuke*; Nakatsuka, Akira*; Nozawa, Shigeki; Hase, Yoshihiro; Narumi, Issei
JAEA-Review 2009-041, JAEA Takasaki Annual Report 2008, P. 77, 2009/12
Kobayashi, Nobuo*; Tasaki, Keisuke*; Kano, Sayaka*; Sakamoto, Sakiko*; Nakatsuka, Akira*; Hase, Yoshihiro; Narumi, Issei
JAEA-Review 2008-055, JAEA Takasaki Annual Report 2007, P. 70, 2008/11
no abstracts in English
Kobayashi, Nobuo*; Sakamoto, Sakiko*; Nakatsuka, Akira*; Hase, Yoshihiro; Narumi, Issei
JAEA-Review 2007-060, JAEA Takasaki Annual Report 2006, P. 87, 2008/03
no abstracts in English
Kobayashi, Nobuo*; Sakamoto, Sakiko*; Nakatsuka, Akira*; Hase, Yoshihiro; Yokota, Yuichiro
JAEA-Review 2006-042, JAEA Takasaki Annual Report 2005, P. 96, 2007/02
no abstracts in English
Sakamoto, Sakiko*; Kobayashi, Nobuo*; Nakatsuka, Akira*; Hase, Yoshihiro; Narumi, Issei
no journal, ,
no abstracts in English
Kano, Sayaka*; Kobayashi, Nobuo*; Nakatsuka, Akira*; Hase, Yoshihiro; Narumi, Issei
no journal, ,
no abstracts in English
Kano, Sayaka*; Kobayashi, Nobuo*; Nakatsuka, Akira*; Nozawa, Shigeki; Hase, Yoshihiro
no journal, ,
no abstracts in English
Masuzaki, Suguru*; Tokitani, Masayuki*; Miyamoto, Mitsutaka*; Nobuta, Yuji*; Ueda, Yoshio*; Ono, Noriyasu*; Sakamoto, Mizuki*; Ashikawa, Naoko*; Nakano, Tomohide; Itami, Kiyoshi
no journal, ,
A design of the movable material probe system for JT-60SA is proposed. The system provides the opportunity for inserting material specimens and diagnostics into the plasma vacuum vessel, and for specimens changing during experimental campaign. The system will consist of manipulator, gate-valves, working chamber and pumps. The system is under consideration to be installed in a bottom port. It will contribute to plasma-wall interaction studies in JT-60SA.
Matsushima, Ryotatsu; Sato, Fuminori; Horiguchi, Kenichi; Kojima, Junji; Yamashita, Masaaki*; Sakai, Etsuo*; Atarashi, Daiki*
no journal, ,
no abstracts in English
Matsushima, Ryotatsu; Sato, Fuminori; Saito, Yasuo; Atarashi, Daiki*
no journal, ,
The Low Radioactive Waste Treatment Technology Development Facility (LWTF) of the Tokai Reprocessing Facility was constructed as a facility for processing low radioactive liquid waste and solid waste generated from the reprocessing facility, and cold tests are being conducted. In this facility, nitrate waste liquor generated with the treatment of liquid waste was made solidified by using borate, but now it is planned to replace it with carbonate waste liquid and then to make cement solidified body. It is studying and designing for equipment introduction. In this report, we investigated the influence of strength and waste composition on change of cement solidified body over time by carrying out cement kneading / solidification test on this carbonate waste liquid on a real scale (200 L drum) will be reported.
Matsushima, Ryotatsu; Sato, Fuminori; Saito, Yasuo; Atarashi, Daiki*
no journal, ,
no abstracts in English
Matsushima, Ryotatsu; Takano, Masato; Atarashi, Daiki*; Saito, Yasuo
no journal, ,
no abstracts in English
Matsushima, Ryotatsu; Takahashi, Kiyofumi; Saito, Yasuo; Kikuchi, Yukihiro*; Atarashi, Daiki*; Shirozu, Hidetomo
no journal, ,
Low Active Waste Treatment Development Facility (LWTF) is planning to solidify the cement waste liquid generated at the Tokai Reprocessing Facility. In the previous report, it has been shown that the carbonate waste liquid can be solidified by conducting a solidification test on the waste liquid simulating the carbonate waste liquid containing sodium carbonate and sodium nitrate. On the other hand, it is expected that sodium sulfate will coexist as a foreign substances in the carbonate waste liquid, even though it is a trace amount, and it has been confirmed that there is no effect of sodium sulfate coexists in beaker-scale test. In this report, a actual-scale test is carried out, confirm that there is no effect when sodium sulfate coexists, and the results is reported. It was confirmed that the presence or absence of sodium sulfate in the waste liquid had no effect on the fluidity of the sample after kneading, the compressive strength of the sample after curing, etc., and thus had no effect on the solidified body properties.