Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Initialising ...
Verzilov, Y. M.; Sato, Satoshi; Ochiai, Kentaro; Wada, Masayuki*; Klix, A.*; Nishitani, Takeo
Fusion Engineering and Design, 82(1), p.1 - 9, 2007/01
Times Cited Count：9 Percentile：54.87(Nuclear Science & Technology)no abstracts in English
Kawamura, Yoshinori; Enoeda, Mikio; Yamanishi, Toshihiko; Nishi, Masataka
Fusion Engineering and Design, 81(1-7), p.809 - 814, 2006/02
Times Cited Count：14 Percentile：68.12(Nuclear Science & Technology)Tritium bred in the solid breeder blanket of a fusion reactor is extracted by passing of a helium sweep gas. Tritium is separated from sweep gas at the blanket tritium recovery system. Palladium membrane diffuser is one of the applicable processes for the blanket tritium recovery system. It is usually applied for hydrogen purification system such as TEP in ITER. However, it has been reported that the rate controlling step changes at lower hydrogen pressure such as the blanket sweep gas condition, and discussion about application for the blanket sweep gas condition is not enough. Recently, conceptual design of the demonstration reactor, named "DEMO2001", has been proposed from JAERI. In this report, the application of the Pd diffuser for the blanket sweep gas condition is discussed based on the condition of DEMO 2001.
Nishitani, Takeo; Yamauchi, Michinori*; Nishio, Satoshi; Wada, Masayuki*
Fusion Engineering and Design, 81(8-14), p.1245 - 1249, 2006/02
Times Cited Count：13 Percentile：65.83(Nuclear Science & Technology)no abstracts in English
Enoeda, Mikio; Akiba, Masato; Tanaka, Satoru*; Shimizu, Akihiko*; Hasegawa, Akira*; Konishi, Satoshi*; Kimura, Akihiko*; Koyama, Akira*; Sagara, Akio*; Muroga, Takeo*
Fusion Engineering and Design, 81(1-7), p.415 - 424, 2006/02
Times Cited Count：62 Percentile：96.4(Nuclear Science & Technology)no abstracts in English
Kikuchi, Mitsuru; Nishio, Satoshi; Kurita, Genichi; Tsuzuki, Kazuhiro; Bakhtiari, M.*; Kawashima, Hisato; Takenaga, Hidenobu; Kusama, Yoshinori; Tobita, Kenji
Fusion Engineering and Design, 81(8-14), p.1589 - 1598, 2006/02
Times Cited Count：4 Percentile：30.68(Nuclear Science & Technology)Blanket-plasma interaction is important for plasma performance enhancement and reliability of first-wall/ blanket. Typical examples are harminization of wall stabilization and reduction of EM force during current quench, error field effect by ferritic steel, neutral-wall interaction under wall saturation, etc. JAERI reactor studies, JT-60U and JFT-2M results on this topics will be described.
Yamauchi, Michinori*; Nishitani, Takeo; Nishio, Satoshi
Denki Gakkai Rombunshi, A, 125(11), p.943 - 946, 2005/11
Considering the geometrical characteristics of tokamak reactors with low aspect ratio, a basic neutronics strategy was derived to construct the inboard structure mainly for neutron shielding and produce enough tritium in the outboard blanket. The designs for optimal inboard shield were surveyed and necessary thickness was estimated to make the neutron flux low enough on the super-conducting magnet. In addition, the outer blanket designs were studied to attain the tritium breeding ratio (TBR) large enough for a self-sustaining fusion reactor on the basis of the advanced fusion reactor materials.
Hegeman, J. B. J.*; Van der Laan, J. G.*; Kawamura, Hiroshi; M
slang, A.*; Kupriyanov, I.*; Uchida, Munenori*; Hayashi, Kimio
Fusion Engineering and Design, 75-79, p.769 - 773, 2005/11
Times Cited Count：26 Percentile：84.04(Nuclear Science & Technology)no abstracts in English
Ochiai, Kentaro; Verzilov, Y. M.; Nishitani, Takeo; Batistoni, P.*; Seidel, K.*
Fusion Science and Technology, 48(1), p.378 - 381, 2005/07
Times Cited Count：7 Percentile：44.9(Nuclear Science & Technology)To evaluate the measurement accuracy of the tritium production from 
LiLi(n,t)
He reactions, an international benchmark program was initiated again under the frame work of an IEA fusion neutronics subtask from 2003. JAERI, ENEA and Technical University of Dresden (TUD) are participating in the activity. This program consists of the calibration of the tritium measurement systems and the verification of the measurement accuracies of the tritium production from 
Li(n,nt)He and LiLi(n,t)He reactions. We have completed the calibration of the measurement system with tritium standard water (HTO) and blind HTO samples. From the results, the scattering of the calibration was within 1.5 %.
Verzilov, Y. M.; Ochiai, Kentaro; Nishitani, Takeo
Fusion Science and Technology, 48(1), p.650 - 653, 2005/07
Times Cited Count：7 Percentile：44.9(Nuclear Science & Technology)no abstracts in English
Kawamura, Yoshinori; Iwai, Yasunori; Nakamura, Hirofumi; Hayashi, Takumi; Yamanishi, Toshihiko; Nishi, Masataka
Fusion Science and Technology, 48(1), p.654 - 657, 2005/07
Times Cited Count：3 Percentile：24.22(Nuclear Science & Technology)Adding some amount of hydrogen to the helium sweep gas is effective for tritium extraction from blanket, but it causes permeation of tritium to a cooling system. In the design study of a demonstration reactor in JAERI, tritium leakage has been estimated to be about 20% of bred tritium under typical sweep gas conditions. If these tritiums are recovered under the ITER-WDS condition, tritium leakage limitation has to be less than 0.3% of typical case. Water vapor addition to the sweep gas is effective not only for blanket tritium extraction but also for permeation prevention. The reaction rate of isotope exchange is larger than the case of H
, and the equilibrium constant is also expected to be about 1.0. When the H/T ratio is 100, tritium inventory of breeder material is larger than the case of H addition. However it is not so large. In case of HO sweep, separation of tritiated water from helium seems to be easyer, but the process that changes HTO to HT is necessary.
Nakamichi, Masaru*; Kawamura, Hiroshi
JAERI-Research 2005-015, 35 Pages, 2005/06
JAERI-Research-2005-015.pdf:6.48MB
no abstracts in English
Enoeda, Mikio; Hatano, Toshihisa; Tsuchiya, Kunihiko; Ochiai, Kentaro; Kawamura, Yoshinori; Hayashi, Kimio; Nishitani, Takeo; Nishi, Masataka; Akiba, Masato
Fusion Science and Technology, 47(4), p.1060 - 1067, 2005/05
Times Cited Count：5 Percentile：35.8(Nuclear Science & Technology)Japan Atomic Energy Research Institute (JAERI) has been assigned as a leading institute for developing the solid breeder blanket in the long-term research program of fusion blankets in Japan, which was approved by the Fusion Council of Japan in 1999. In accordance with the long term research program, element technology development of solid blanket has been performed at JAERI and showed significant progress. Based on the achievement of the element technology development, the development phase is now stepping further to the engineering development phase. This paper presents the major achievements of the element technology development of solid breeder blanket in JAERI.
Enoeda, Mikio; Akiba, Masato; Tanaka, Satoru*; Shimizu, Akihiko*; Hasegawa, Akira*; Konishi, Satoshi*; Kimura, Akihiko*; Koyama, Akira*; Sagara, Akio*; Muroga, Takeo*
Fusion Science and Technology, 47(4), p.1023 - 1030, 2005/05
Times Cited Count：4 Percentile：30.51(Nuclear Science & Technology)The Fusion Council of Japan has established the long-term research and development program of the blanket in 1999. In the program, the solid breeder blanket was selected as the primary candidate blanket of the fusion power demonstration plant in Japan. In the program, Japan Atomic Energy Research Institute (JAERI) has been nominated as a leading institute of the development of solid breeder blankets, in collaboration with universities, for the near term power demonstration plant, while, universities including National Institute for Fusion Science (NIFS) are assigned mainly to develop advanced blankets for longer term power plant development. In the long term research and development program, ITER blanket module testing is identified as the most important milestone, by which integrity of candidate blanket concepts and structures are evaluated. In Japan, universities, NIFS and JAERI cover a variety of types of blanket development. This paper presents a plan and strategy for ITER blanket module testing in Japan.
Department of Fusion Engineering Research
JAERI-Review 2005-011, 139 Pages, 2005/03
JAERI-Review-2005-011.pdf:11.95MB
no abstracts in English
Verzilov, Y. M.; Sato, Satoshi; Nakao, Makoto*; Ochiai, Kentaro; Wada, Masayuki*; Nishitani, Takeo
JAERI-Research 2004-015, 55 Pages, 2004/10
JAERI-Research-2004-015.pdf:3.29MB
no abstracts in English
Furuya, Kazuyuki
JAERI-Research 2004-013, 165 Pages, 2004/09
JAERI-Research-2004-013.pdf:53.73MB
no abstracts in English
Enoeda, Mikio
Koon Gakkai-Shi, 30(5), p.256 - 262, 2004/09
Fabrication technologies for ITER in-vessel components, especially the shielding blanket with the separable first wall panel has been developed. Hot Isostatic Pressing (HIP) has been applied to the bonding of Cu-alloy/stainless steel and beryllium/Cu-alloy. First wall mock-ups fabricated by using HIP were tested under high heat fluxes and showed sufficient heat removal and thermal fatigue performance. Water jet and electrical discharge machining have been applied to manufacture slots into the first wall panel and the shield block. With these technologies, a first wall panel prototype and a shielding block 1/2 mock-up were successfully fabricated.
Sato, Satoshi; Tanaka, Teruya*; Hori, Junichi; Ochiai, Kentaro; Nishitani, Takeo; Muroga, Takeo*
Journal of Nuclear Materials, 329-333(Part2), p.1648 - 1652, 2004/08
Times Cited Count：2 Percentile：17.18(Materials Science, Multidisciplinary)no abstracts in English
Verzilov, Y. M.; Ochiai, Kentaro; Klix, A.; Sato, Satoshi; Wada, Masayuki*; Yamauchi, Michinori*; Nishitani, Takeo
Journal of Nuclear Materials, 329-333(Part2), p.1337 - 1341, 2004/08
Times Cited Count：4 Percentile：29.26(Materials Science, Multidisciplinary)no abstracts in English
Fusion Neutron Laboratory
JAERI-Review 2004-017, 163 Pages, 2004/07
JAERI-Review-2004-017.pdf:25.47MB
no abstracts in English
