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Komatsu, Teruhisa; Adachi, Takeo
Journal of Applied Meteorology, 42(9), p.1330 - 1334, 2003/09
no abstracts in English
*; Mihara, Morihiro;
JNC TN8430 2001-007, 56 Pages, 2002/01
In the geological disposal concept of radioactive wastes, a kind of clay with sorption ability and low permeability, called bentonite, is envisaged as an engineered barrier system in the geological repository. Also, the cemetitious material is envisaged as the backfill material in the vaults and the structure material of the vaults. The groundwater in contact with the cementitious material will promote hyperalkaline conditions in the repository environment and these conditions will affect the performance of the bentonite. Therefore, it is necessary to investigate the interaction between the cementitious material and the bentonite for the evaluation of long term stability of the disposal system. In this study, for the identification and the investigation of the secondary minerals, the batch immersion experiments of the powder bentonite were carried out using synthetic cement leachates (pH=7, 12.5, 14) at 200C. As the results, it was confirmed that Na as exchangeable cations in the bentonite can exchange relatively easily with Ca in the solution from the experiment results. And the ratio of cation exchange was estimated to be about 25% based on the amount of exchangeable cations Ca between layers. Furthermore, it was concretely shown that the generation of analcime might be affected by the Na concentration from results of the solution analyses and a stability analysis of analcime using the chemical equilibrium model, in addition to the pH in the solution.
Komatsu, Teruhisa
Journal of the Physical Society of Japan, 70(12), p.3755 - 3756, 2001/12
Times Cited Count:4 Percentile:33.15(Physics, Multidisciplinary)no abstracts in English
Komatsu, Teruhisa; Inagaki, Shio*; Nakagawa, Naoko*; Nasuno, Satoru*
Physical Review Letters, 86(9), p.1757 - 1760, 2001/02
Times Cited Count:251 Percentile:97.47(Physics, Multidisciplinary)no abstracts in English
; *; Sakurai, Koji*; ; Nomura, Kazunori; *
JNC TN8400 2000-032, 98 Pages, 2000/12
Concerning the preparation of high U solution for the crystallization process and the application of UO powder dissolution to that, the effects of final U concentration, dissolution temperature, nitric acid concentration and powder size on the dissolution of UO powder in the nitric acid where the final U concentration was 800g/L were investigated. The experimental results showed that the solubility of UO decreased with the increase of final UO concentration and powder size, and with the decrease of dissolution temperature and nitric acid concentration. It was also confirmed that in the condition where the final U concentration was sufficiently lower than the solubility of U, UO dissolution behavior in the high U solution could be estimated with the equation based on the fragmentation model which we had already reported. Based on these experimental results, the dissolution behavior of irradiated MOX fuel in high U solution was estimated and the possibility of supplying high U solution to the crystallization process was discussed. In the preparation of high U solution for the crystallization process, it was estimated that the present dissolution process (dissolution for fuel pieces of about 3cm long) needed a lot of time to obtain a high dissolution yield, but it was shorted drastically by the pulverization of fuel pieces. The burst of off-gas at the early in the dissolution of fuel powder seems to be avoidable with setting the appropriate dissolution condition, and it is important to optimize the dissolution condition with considering the capacity of off-gas treatment process.
Tokuoka, Naochika*; Kobayashi, Mamoru*; Koyama, Takashi*
PNC TJ1636 96-001, 64 Pages, 1996/03
None
; Kaetsu, Isao
Int.J.Appl.Radiat.Isot., 35(1), p.21 - 24, 1984/00
Times Cited Count:6 Percentile:57.41(Nuclear Science & Technology)no abstracts in English
; ;
Journal of Nuclear Science and Technology, 20(7), p.603 - 610, 1983/00
Times Cited Count:4 Percentile:50.99(Nuclear Science & Technology)no abstracts in English
; ;
Kogai To Taisaku, 19(2), p.158 - 164, 1983/00
no abstracts in English
; ; ;
Journal of Nuclear Science and Technology, 19(3), p.222 - 230, 1982/00
Times Cited Count:12 Percentile:75.26(Nuclear Science & Technology)no abstracts in English
*; ; ;
Int.J.Appl.Radiat.Isot., 30(1), p.51 - 54, 1979/00
no abstracts in English
; Wadachi, Yoshiki
Nihon Genshiryoku Gakkai-Shi, 18(5), p.286 - 291, 1976/05
no abstracts in English
JAERI-M 6392, 48 Pages, 1976/02
no abstracts in English
; Ito, Hiroshi; Yoshida, Kenzo; Araki, Kunio
JAERI-M 6020, 33 Pages, 1975/03
no abstracts in English
Yamaguchi, Koichi; Takehisa, Masaaki
JAERI-M 5524, 32 Pages, 1974/01
no abstracts in English
Yoshida, Kenzo; ; ; *; ; Ito, Hiroshi; Araki, Kunio
JAERI-M 4796, 31 Pages, 1972/04
no abstracts in English
Akaoka, Katsuaki; Oba, Masaki; Miyabe, Masabumi; Wakaida, Ikuo
no journal, ,
no abstracts in English