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Ono, Hirokazu; Ishii, Eiichi
Geomechanics for Energy and the Environment, 31, p.100317_1 - 100317_9, 2022/09
Times Cited Count：9 Percentile：59.03(Energy & Fuels)Kato, Masaji*; Nara, Yoshitaka*; Okazaki, Yuki*; Kono, Masanori*; Sato, Toshinori; Sato, Tsutomu*; Takahashi, Manabu*
Zairyo, 67(3), p.318 - 323, 2018/03
To ensure the safe geological disposal of radioactive wastes, it is important to determine the permeability of clays. The transient pulse test is suitable to apply to the low permeability materials, because it takes relatively short term to determine the permeability. Usually we increase the upstream pore pressure in the measurement with the transient pulse test. However, it is impossible to determine the permeability of clay in this procedure because of the increase of pore pressure. Therefore, the transient pulse test has never been applied to the determination of permeability of clays. In this study, we tried to apply the transient pulse test to a clay obtained in Mizunami Underground Research Laboratory to determine the permeability with decreasing the downstream pore pressure. It was clarified that the transient pulse test with decreasing downstream pore pressure is appropriate from the measurements of granite and sandstone. It was shown that the permeability of a clay was determined by the transient pulse test with decreasing the downstream pore pressure, which agreed with the permeability determined from the falling head test. The measurement time of the transient pulse test is much shorter than that of the falling head test. It is concluded that the transient pulse test is appropriate for the determination of the permeability of clays.
Takamatsu, Kuniyoshi
Annals of Nuclear Energy, 106, p.71 - 83, 2017/08
The HTTR, which is the only HTGR having inherent safety features in Japan, conducted a safety demonstration test involving a loss of both reactor reactivity control and core cooling. The paper shows thermal-hydraulics during the LOFC test at an initial power of 30% reactor power (9 MW), when the insertion of all control rods was disabled and all gas circulators were tripped to reduce the coolant flow rate to zero. The analytical results could show that the downstream of forced convection caused by the HPS pushes down the upstream by natural convection in the fuel assemblies; however, the forced convection has little influence on the core thermal-hydraulics without the reactor outlet coolant temperature. As a result, the three-dimensional thermal-phenomena inside the RPV during the LOFC test could be understood qualitatively.
Takamatsu, Kuniyoshi
Journal of Thermal Science, 24(3), p.295 - 301, 2015/06
Times Cited Count：2 Percentile：10.19(Thermodynamics)Before rise-to-power tests, the actual measured value of heat released from the Reactor Pressure Vessel (RPV) or removed by the Vessel Cooling System (VCS) cannot be obtained. It is difficult for operators to evaluate the reactor outlet coolant temperature supplied from the High Temperature Engineering Test Reactor (HTTR) before rise-to-power tests. Therefore, when the actual measured value of heat released from the RPV or removed by the VCS are changed during rise-to-power tests, operators need to evaluate quickly, within a few minutes, the heat removed by the VCS and the reactor outlet coolant temperature of 30 (MW), at the 100% of the reactor power, before the temperature achieves to 967 (
C) which is the maximum temperature limit generating the reactor scram. In this paper, a rapid evaluation method for use by operators is presented.
Kunitomi, Kazuhiko; Tachibana, Yukio; Takeda, Takeshi; Saikusa, Akio; Sawa, Kazuhiro
JAERI-Tech 97-030, 60 Pages, 1997/07
no abstracts in English
Takeda, Takeshi; Kunitomi, Kazuhiko; Okubo, Minoru
Nihon Genshiryoku Gakkai-Shi, 38(4), p.307 - 314, 1996/00
no abstracts in English
; ; ; Yamamoto, Katsumune; Oyamada, Rokuro; Saito, Minoru
JAERI-M 94-042, 0, p.305 - 312, 1994/03
no abstracts in English
Iwamura, Takamichi; Watanabe, Hironori; Okubo, Tsutomu; Araya, Fumimasa; Murao, Yoshio
Journal of Nuclear Science and Technology, 30(5), p.413 - 424, 1993/05
Times Cited Count：2 Percentile：29.37(Nuclear Science & Technology)no abstracts in English
Iwamura, Takamichi; Watanabe, Hironori; Araya, Fumimasa; Okubo, Tsutomu; Murao, Yoshio
JAERI-M 92-050, 46 Pages, 1992/03
no abstracts in English
Kukita, Yutaka
Genshiryoku Kogyo, 38(5), p.8 - 16, 1992/00
no abstracts in English
Kukita, Yutaka; Anoda, Yoshinari;
Nucl. Eng. Des., 131, p.101 - 111, 1991/00
Times Cited Count：25 Percentile：90.35(Nuclear Science & Technology)no abstracts in English
Tasaka, Kanji; Koizumi, Yasuo; Suzuki, Mitsuhiro; Anoda, Yoshinari; Kukita, Yutaka; Kumamaru, Hiroshige; Nakamura, Hideo; Yonomoto, Taisuke; Kawaji, Masahiro; Murata, Hideo
JAERI 1307, 379 Pages, 1987/11
no abstracts in English
JAERI-M 85-122, 126 Pages, 1985/08
no abstracts in English
Kaminaga, Masanori; ; ; Sudo, Yukio
JAERI-M 85-071, 65 Pages, 1985/06
no abstracts in English
Sudo, Yukio; ; ;
JAERI-M 84-119, 108 Pages, 1984/06
no abstracts in English
; ; ; ;
JAERI-M 9405, 121 Pages, 1981/03
no abstracts in English
; ; ; ;
JAERI-M 8961, 121 Pages, 1980/07
no abstracts in English
Koizumi, Yasuo; Soda, Kunihisa; ; Tasaka, Kanji;
JAERI-M 8899, 110 Pages, 1980/07
no abstracts in English
; ; ; ;
JAERI-M 8887, 132 Pages, 1980/06
no abstracts in English
; Koizumi, Yasuo; Soda, Kunihisa; Tasaka, Kanji
JAERI-M 8729, 106 Pages, 1980/03
no abstracts in English
