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Murakami, Hiroshi
Chemical Physics Letters, 417(4-6), p.550 - 554, 2006/01
Times Cited Count：5 Percentile：15.48(Chemistry, Physical)no abstracts in English
Department of Fusion Engineering Research
JAERI-Review 2005-011, 139 Pages, 2005/03
JAERI-Review-2005-011.pdf:11.95MB
no abstracts in English
Hirai, Takeshi*; Ezato, Koichiro; Majerus, P.*
Materials Transactions, 46(3), p.412 - 424, 2005/03
Times Cited Count：113 Percentile：88.24(Materials Science, Multidisciplinary)no abstracts in English
Nemoto, Yoshiyuki; Hasegawa, Akira*; Sato, Manabu*; Abe, Katsunori*; Hiraoka, Yutaka*
Journal of Nuclear Materials, 324(1), p.62 - 70, 2004/01
Times Cited Count：50 Percentile：93.40(Materials Science, Multidisciplinary)In this study, stress-relieved specimens and recrystallized specimens of pure Mo and Mo-Re alloys (Re content=2,4,5,10,13 and 41wt%) were neutron irradiated up to 20dpa at various temperatures (681-1072K). On microstructure observation, sigma phase and chi phase precipitates were observed in all irradiated Mo-Re alloys. Voids were observed in all irradiated specimen, and dislocation loops and dislocations were observed in the specimens that were irradiated at lower temperatures. On Vickers hardness testing, all of the irradiated specimens showed hardening. Especially Mo-41Re were drastically embrittled after irradiation at 874K or less. From these results, authors discuss about relation between microstructure development and radiation hardening, embrittlement, and propose the most efficient Re content and thermal treatment for Mo-Re alloys to be used under irradiation condition.
Research Committee for Fusion Reactor; Research Committee for Fusion Materials
JAERI-Review 2003-015, 123 Pages, 2003/05
JAERI-Review-2003-015.pdf:24.89MB
no abstracts in English
IFMIF International Team
JAERI-Tech 2003-005, 559 Pages, 2003/03
JAERI-Tech-2003-005.pdf:48.89MB
The International Fusion Materials Irradiation Facility (IFMIF) is an accelerator-based D-Li neutron source designed to produce an intense neutron field that will simulate the neutron environment of a D-T fusion reactor. IFMIF will provide a neutron flux equivalent to 2 MW/m
, 20 dpa/y in Fe, in a volume of 500 cm
and will be used in the development and qualification of materials for fusion systems. The design activities of IFMIF are performed under an IEA collaboration which began in 1995. In 2000, a three-year Key Element Technology Phase (KEP) of IFMIF was undertaken to reduce the key technology risk factors. This KEP report describes the results of the three-year KEP activities in the major project areas of accelerator, target, test facilities and design integration.
Ogawa, Hiroaki*; Kiuchi, Kiyoshi
JAERI-Research 2002-037, 48 Pages, 2002/12
JAERI-Research-2002-037.pdf:2.57MB
The difference in hydrogen permeation among candidate cladding materials such as 25Cr-35Ni stainless steel, Nb liner and reference materials such as 18Cr-8Ni SS, and Zr of Zircaloy base metal were evaluated by low energy plasma permeation simulated to hydrogen excited by heavy neutron irradiation. RF excitation source was arranged for the experimental apparatus in cooperating with temperature and bias control. Comparing with the thermodynamic gas driven permeation (GDP) in the same hydrogen pressure, the hydrogen permeation rate by the plasma driven permeation (PDP) was markedly accelerated at low to medium temperature range. The temperature dependency showed a knick at around 530K due to hydrogen-defect interactions. Comparing with Zr, Nb showed the high hydrogen solubility without the degradation by hydrate formation that is required to a getter material. The difference in PDP among candidates was analyzed with a new dissolution model for hydrogen.
Hori, Junichi; Maekawa, Fujio; Wada, Masayuki*; Ochiai, Kentaro; Yamauchi, Michinori*; Morimoto, Yuichi*; Terada, Yasuaki; Klix, A.; Nishitani, Takeo
Fusion Engineering and Design, 63-64, p.271 - 276, 2002/12
Times Cited Count：2 Percentile：16.38(Nuclear Science & Technology)In order to the waste management method and the safety design of future D-T fusion reactor, it is important to consider the radioactivity productions via not only primary neutron reactions but also sequential charged particle reactions (SCPR). Especially, on the surface of a coolant channel many recoiled protons are generated by the neutron irradiation with coolant water, so it is apprehensive that the undesirable radioactive nuclide production yields via SCPR are enhanced. In this work, the laminated sample pieces of fusion material foils (V, Fe, W, Ti, Pb, Cu) were made and attached on a polyethylene board to simulate water flowing inside a coolant channel. They were irradiated with D-T neutrons. The effective radioactivity cross section and the depth distribution of the radioactivity production yields due to SCPR were obtained for each material. On the other hand, the estimated values were compared with the experimental ones.
Research Committee for Fusion Reactor; Research Committee for Fusion Materials
JAERI-Review 2002-008, 79 Pages, 2002/03
JAERI-Review-2002-008.pdf:9.92MB
Joint research committee for fusion reactor and materials was held in Tokyo on July 16, 2001. In the committee, a review of the development programs and the present status on the blanket technology, materials and IFMIF(International Fusion Materials Irradiation Facility) in JAERI and Japanese Universities was reported, and the direction of these R&D was discussed. Moreover, the progress of the collaboration between JAERI and Japanese Universities was discussed. This report consists of the summaries of the presentations and the viewgraphs which were used at the committee.
HTTR Utilization Research Committee
JAERI-Review 2001-016, 232 Pages, 2001/05
JAERI-Review-2001-016.pdf:12.01MB
no abstracts in English
Yamada, Reiji; Taguchi, Tomitsugu; Igawa, Naoki
Journal of Nuclear Materials, 283-287(Part.2), p.574 - 578, 2000/12
Times Cited Count：75 Percentile：96.88(Materials Science, Multidisciplinary)no abstracts in English
Committee for the Joint Research Project on the Advanced Radiation Technology; Committee for the Collaborative Research on the Advanced Radiation Technology
JAERI-Conf 2000-008, 113 Pages, 2000/06
JAERI-Conf-2000-008.pdf:11.5MB
no abstracts in English
Seki, Yasushi; Aoki, Isao; Ueda, Shuzo; Nishio, Satoshi; Kurihara, Ryoichi; Tabara, Takashi*
Fusion Technology, 34(3), p.353 - 357, 1998/11
no abstracts in English
Oyama, Yukio; Noda, Kenji; Kosako, Kazuaki*
Fusion Engineering and Design, 42, p.437 - 442, 1998/00
Times Cited Count：2 Percentile：24.18(Nuclear Science & Technology)no abstracts in English
Kondo, Tatsuo; Ono, Hideo; R.A.Jameson*; J.A.Hassberger*
Fusion Engineering and Design, 22, p.117 - 127, 1993/00
Times Cited Count：6 Percentile：55.59(Nuclear Science & Technology)no abstracts in English
; ; Seki, Yasushi
Purazuma, Kaku Yugo Gakkai-Shi, 68(5), p.511 - 515, 1992/11
no abstracts in English
Ono, Hideo
Journal of Nuclear Materials, 179-181, p.60 - 63, 1991/00
Times Cited Count：5 Percentile：53.57(Materials Science, Multidisciplinary)no abstracts in English
Murakami, Yoshio; Abe, Tetsuya
J.Vac.Sci.Technol.,A, 5(4), p.2305 - 2310, 1987/04
no abstracts in English
Hyomen Kagaku, 7, p.422 - 423, 1986/00
no abstracts in English
JAERI-M 85-204, 7 Pages, 1985/12
no abstracts in English
