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Sugita, Yutaka; Aoyagi, Kazuhei; Kubota, Kenji*; Nakata, Eiji*; Oyama, Takahiro*
JAEA-Research 2018-002, 72 Pages, 2018/06
JAEA-Research-2018-002.pdf:6.16MB
In a excavation of shafts and galleries in the deep underground for disposing radioactive waste, an excavation damaged zone (EDZ) is developed around the galleries and shafts owing to the stress redistribution. Since the characteristic changes of the rock mass in the EDZ affects the radionuclides migration behavior, it is important to understand the long-term behavior of the EDZ. Thus, we performed the in situ experiment to investigate the long-term behavior of EDZ as part of the collaborative research between Japan Atomic Energy Agency and Central Research Institute of Electric Power Industry in the 140m gallery in the Horonobe Underground Research Laboratory. In this research, we investigated the extent, mechanism of the change of hydro-mechanical characteristic, and long-term behavior of the EDZ on the basis of the comprehensive estimation of the results of the observation of the drift wall and the various investigations using boreholes such as geological investigation, the seismic and resistivity tomography, hydraulic test, water content monitoring, borehole loading test, convergence measurement, and so on. In addition, we clarified applicability and future tasks of the testing method used in this research for the investigation of the long-term behavior of the EDZ.
Irisawa, Keita; Meguro, Yoshihiro
Journal of Nuclear Science and Technology, 54(3), p.365 - 372, 2017/03
Times Cited Count：2 Percentile：19.37(Nuclear Science & Technology)Kobayashi, Fuyumi; Sumiya, Masato; Kida, Takashi; Kokusen, Junya; Uchida, Shoji; Kaminaga, Jota; Oki, Keiichi; Fukaya, Hiroyuki; Sono, Hiroki
JAEA-Technology 2016-025, 42 Pages, 2016/11
JAEA-Technology-2016-025.pdf:17.88MB
A preliminary test on MOX fuel dissolution for the STACY critical experiments had been conducted in 2000 through 2003 at Nuclear Science Research Institute of JAEA. Accordingly, the uranyl / plutonium nitrate solution should be reconverted into oxide powder to store the fuel for a long period. For this storage, the moisture content in the oxide powder should be controlled from the viewpoint of criticality safety. The stabilization of uranium / plutonium solution was carried out under a precipitation process using ammonia or oxalic acid solution, and a calcination process using a sintering furnace. As a result of the stabilization operation, recovery rate was 95.6% for uranium and 95.0% for plutonium. Further, the recovered oxide powder was calcined again in nitrogen atmosphere and sealed immediately with a plastic bag to keep its moisture content low and to prevent from reabsorbing atmospheric moisture.
Nakamura, Jinichi; Sugiyama, Tomoyuki; Nakamura, Takehiko; Kanazawa, Toru; Sasajima, Hideo
JAERI-Tech 2003-008, 32 Pages, 2003/03
JAERI-Tech-2003-008.pdf:1.49MB
no abstracts in English
Takada, Eiji*; Sumita, Junya; Sawa, Kazuhiro; Tada, Keiko*
JAERI-Tech 2000-020, p.65 - 0, 2000/03
JAERI-Tech-2000-020.pdf:2.12MB
no abstracts in English
*; *; Saido, Masahiro; Ogiwara, Norio; *
Japanese Journal of Applied Physics, 32(9A), p.3968 - 3974, 1993/09
Times Cited Count：14 Percentile：60.83(Physics, Applied)no abstracts in English
Nagao, Seiya; *
Geochemical Journal, 25, p.187 - 197, 1991/00
Times Cited Count：12 Percentile：37.19(Geochemistry & Geophysics)no abstracts in English
M.S.Rahman*; Kume, Tamikazu; Ishigaki, Isao
JAERI-M 89-197, 14 Pages, 1989/12
no abstracts in English
; *; *; *; Kondo, Tatsuo
Proc.Int.Conf.on Creep, p.97 - 102, 1986/00
no abstracts in English
and PuCoC; ; ;
Journal of Nuclear Science and Technology, 19(3), p.257 - 260, 1982/00
Times Cited Count：3 Percentile：54.87(Nuclear Science & Technology)no abstracts in English
powdersShiba, Koreyuki; ; Ugajin, Mitsuhiro
Journal of Nuclear Materials, 96(3), p.255 - 260, 1981/00
Times Cited Count：6 Percentile：62.77(Materials Science, Multidisciplinary)no abstracts in English
; ;
Journal of Nuclear Science and Technology, 18(10), p.802 - 810, 1981/00
Times Cited Count：15 Percentile：84.09(Nuclear Science & Technology)no abstracts in English
; ; ; ;
JAERI-M 8497, 27 Pages, 1979/10
no abstracts in English
; ;
JAERI-M 8081, 26 Pages, 1979/02
no abstracts in English
; ; ;
Journal of Nuclear Science and Technology, 15(2), p.152 - 155, 1978/02
Times Cited Count：1no abstracts in English
Ogawa, Yutaka; Kondo, Tatsuo; ;
Proc.of 2nd Japan-US HTGR Safety Technology Seminar,Material Properties and Design Method Session, 9 Pages, 1978/00
no abstracts in English
Sasuga, Tsuneo; Takehisa, Masaaki
J.Polym.Sci.,Polym.Phys.Ed., 12(9), p.1889 - 1898, 1974/09
no abstracts in English
