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Fukuda, Yuji; Akahane, Yutaka; Aoyama, Makoto; Inoue, Norihiro*; Ueda, Hideki; Nakai, Yoshiki*; Tsuji, Koichi*; Yamakawa, Koichi; Hironaka, Yoichiro*; Kishimura, Hiroaki*; et al.
Applied Physics Letters, 85(21), p.5099 - 5101, 2004/11
Times Cited Count：11 Percentile：42.77(Physics, Applied)We have demonstrated diffraction from Si(111) crystal using X-rays from highly ionized Ar ions produced by laser irradiation with an intensity of 6
10
W/cm
and a pulse duration of 30 fs acting upon micron-sized Ar clusters. The measured total photon flux and line width in the He
line (3.14 keV) were 410
photons/shot/4
sr and 3.7 eV (FWHM), respectively, which is sufficient to utilize as a debris-free light source for time-resolved X-ray diffraction studies.
C in dry oxygen ambient on silicon carbide and their thermal annealing effectsYoshikawa, Masahito; Ishida, Yuki*; Jikimoto, Tamotsu*; Hijikata, Yasuto*; Ito, Hisayoshi; Okumura, Hajime*; Takahashi, Tetsuo*; Tsuchida, Hidekazu*; Yoshida, Sadafumi*
Denshi Joho Tsushin Gakkai Rombunshi, C, 86(4), p.426 - 433, 2003/04
no abstracts in English
Urano, Hajime*; Kamada, Yutaka; Shirai, Hiroshi; Takizuka, Tomonori; Kubo, Hirotaka; Takenaga, Hidenobu; Miura, Yukitoshi; Hatae, Takaki; Fukuda, Takeshi
Plasma Physics and Controlled Fusion, 44(5A), p.A437 - A443, 2002/05
Times Cited Count：18 Percentile：50.83(Physics, Fluids & Plasmas)no abstracts in English
Kubo, Hirotaka; Sakurai, Shinji; Asakura, Nobuyuki; Konoshima, Shigeru; Tamai, Hiroshi; Higashijima, Satoru; Sakasai, Akira; Takenaga, Hidenobu; Itami, Kiyoshi; Shimizu, Katsuhiro; et al.
Nuclear Fusion, 41(2), p.227 - 233, 2001/02
Times Cited Count：53 Percentile：81.56(Physics, Fluids & Plasmas)no abstracts in English
Urano, Hajime; Kamada, Yutaka; Kubo, Hirotaka; Sakurai, Shinji; Shirai, Hiroshi; Takizuka, Tomonori; Hatae, Takaki; Ide, Shunsuke; Fujita, Takaaki; Fukuda, Takeshi
Journal of Plasma and Fusion Research SERIES, Vol.4, p.239 - 242, 2001/00
no abstracts in English
Isogai, Takeshi*; Oda, Chie
JNC TN8400 2000-025, 48 Pages, 2000/09
Porewater chemistly in compacted bentonite would affect a performance of engineered barrier system in a high-level radioactive waste repository, whereas there are little information of the porewater based on experimental data. The previous study provided a new method of direct pH measurement for highly compacted bentonite system and demonstrated some tests for compacted bentonite samples (the dry densities: 1.6 [g/cm
] and 1.8 [g/cm]) both with the de-ionized water and with the NaCl solution. In this study, the solution equilibrated with low alkalinity cement were used in the direct pH measurement to see the effect of the composition of the external solutions, in which the bentonite column immersed. The result showed that the pH value of porewater in the cementitious condition was around 9 during the immersed time 1 to 3 months, while after 6 months became the porewater pH 10.6, which was equal to pH of the external solution.
Shimizu, Futoshi; Kimizuka, Hajime*; Kaburaki, Hideo; Li, J.*; Yip, S.*
Proceedings of 4th International Conference on Supercomputing in Nuclear Applications (SNA 2000) (CD-ROM), 10 Pages, 2000/09
no abstracts in English
Kakehi, Isao; Tozawa, Katsuhiro; ; ; *
JNC TN9400 2000-053, 99 Pages, 2000/04
JNC-TN9400-2000-053.pdf:7.47MB
This report describes accomplishment of simulations of Pyrochemical Process Operation by using virtual engineering models. The pyrochemical process using molten salt electrorefining would introduce new technologies for new fuels of particle oxide, particle nitride and metallic fuels. This system is a batch treatment system of reprocessing and re-fabrication, which transports products of solid form from a process to next process. As a result, this system needs automated transport system for process operations by robotics. ln this study, a simulation code system has been prepared, which provides virtual engineering environment to evaluate the pyrochemical process operation of a batch treatment system using handling robots. And the simulation study has been conducted to evaluate the required system functions, which are the function of handling robots, the interactions between robot and process equipment, and the time schedule of process, in the automated transport system by robotics. As a result of simulation of the process operation, which we have designed, the automated transport system by robotics of the pyrochemical process is realistic. And the issues for the system development have been pointed out.
; Washiya, Tadahiro;
JNC TN8420 2001-009, 48 Pages, 2000/04
JNC-TN8420-2001-009.pdf:0.58MB
ICONE(International Conference on Nuclear Engineering) is an international conference on nuclear chemical engineering held among the United States, Japan and Europe, and ICONE8 (the 8th time of the conference) was held at Baltimore, USA on April 2 to 6, 2000. The authors of this paper reported the latest information on the reprocessing technology in the following session of the conference and audited the panel discussion and the technical report of the dry reprocessing technology etc. in the conference. (1)Investigation of Safety Evaluation Method and Application to Tokai Reprocessing Plant (TRP) in session of Track-5 "Non-reactor Safety and Reliability" (Nakamura) (2)Structural Improvement on the continuous rotary dissolver in session of Track-9 "Spent Nuclear Fuel and Waste Processing" (Washiya) (3)Development of Evaporators Made of Ti-5% Ta Alloy and Zr - Endurance Test By Mock-Up unit" in session of Track-2 "Aging and Modeling of Component Aging, Including corrosion of Metals and Welds.. passivation, and passive films" (Takata) At the conference, about 650 people participated from the United States, Japan, France, Canada and others, about700 research announcements, 7 keynote lecture and 8 panel discussion were done, flourishing with many participants. Moreover, as the conference was held in the year of 2000, the evaluation of this century and the direction of the next century of nuclear energy were discussed. After the conference, authors visited Argonne National Laboratory (ANL-E, ANL-W) and exchanged information concerning dry process with researchers of ANL-E and ANL-W, visiting ANL facilities. It was very significant to be able to acquire the information on the dry process developed in ANL and realize the device scale and the development environment, etc. and acquire technical information in detail which would not be able to obtain by engineering data, exchanging information with ANL engineers directly. It is suggested to be very valuable that the ...
Fujita, Takaaki; JT-60 Team
Journal of Plasma and Fusion Research SERIES, Vol.3, p.87 - 93, 2000/00
no abstracts in English
Sakasai, Akira; Takenaga, Hidenobu; Hosogane, Nobuyuki; Kubo, Hirotaka; Sakurai, Shinji; Akino, Noboru; Fujita, Takaaki; Higashijima, Satoru; Tamai, Hiroshi; Asakura, Nobuyuki; et al.
Fusion Energy 1998 (CD-ROM), 8 Pages, 1999/00
no abstracts in English
Sakasai, Akira; Takenaga, Hidenobu; Hosogane, Nobuyuki; Sakurai, Shinji; Akino, Noboru; Kubo, Hirotaka; Higashijima, Satoru; Tamai, Hiroshi; Asakura, Nobuyuki; Itami, Kiyoshi; et al.
Journal of Nuclear Materials, 266-269, p.312 - 317, 1999/00
Times Cited Count：18 Percentile：77.26(Materials Science, Multidisciplinary)no abstracts in English
Sagawa, Norihiko*
PNC TJ9613 97-002, 95 Pages, 1997/10
The diffusion coefficient of cesium iodide vapor in rare gases was determined by a modified Stefan's method. The rare gas in a diffusion column was saturated with vapor of the cesium iodide, crystals of which were heated to melt at the bottom of the column. By opening a valve united at a top of the column, the vapor diffusing through the column was transferred with the carrier rare gas to an ionization sensor. The concentration of cesium iodide in the carrier gas was continuously monitored with the sensor. The diffusion coefficient was determined by analyzing the transient response of the concentration. Increasing tendency with temperature is observed in the coefficients obtained in argon, kripton and xenon at temperatures between 631 and 691 C and no significant difference among the coefficients in argon, krypton and xenon.
Sagawa, Norihiko*
PNC TJ9613 97-001, 90 Pages, 1997/10
An ionization sensor. which ionizes iodine vapor on a heated filament and collects ionized iodine on a collector at positive potential, was made on an experimental basis. Iodine vapor in rare gas was determined with using the sensor on the line and the characteristic of the sensor was examined. Iodine vapor was generated from iodine crystals in an iodine evaporator and transferred to the sensor with carrier-rare gas. The iodine vapor was continuously monitored by the sensor and trapped in solution of sodium hydroxide. The amount of iodine in the solution was determined by chemical analyses. The integrated value of ion current was compared with the collected amount of the iodine. A proportional relation is observed between the collected amount and the integrated value obtained from the sensor with a platinum collector, but not found between the amount and the value obtained from the sensor with a stainless steel collector.
Yoneda, Yoshihiro*; Takahara, Hiroyuki*; Nakamura, Naoaki*; Akiyama, Shinsuke*; Moriya, Toshifumi*; Negi, Tateyuki*
PNC TJ1380 97-001, 1338 Pages, 1997/03
None
H+D
in an argon matrix at 20K*; Kumada, Takayuki; Aratono, Yasuyuki; Miyazaki, Tetsuro*
Chemical Physics Letters, 268(5-6), p.493 - 497, 1997/00
Times Cited Count：15 Percentile：47.5(Chemistry, Physical)no abstracts in English
Sakurai, Tsutomu
Journal of Nuclear Science and Technology, 33(3), p.266 - 267, 1996/03
no abstracts in English
