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Yamanishi, Toshihiko
Purazuma, Kaku Yugo Gakkai-Shi, 92(1), p.21 - 25, 2016/01
In a fusion reactor, the hydrogen isotope separation system is required in the fuel cycle system to supply deuterium (D) and tritium (T) as its fuel. In ITER, 90% of T must be recycled through the isotope separation system. On the other hand; since the hydrogen (H) gas is finally exhausted to the environment, the T concentration in the H gas from the isotope separation system should be as low as reasonable achievable. Hence, the isotope separation system of a fusion reactor must have a large separation factor. The flow rate of the isotope separation system of a fusion reactor reaches to 300 mol/h. Only the cryogenic distillation method can meet the above conditions (large flow rate and separation factor) and is most likely used as a hydrogen separation system in a fusion reactor. In this chapter, several simulation methods and a set of experimental data of the cryogenic distillation columns are described in detail.
Nishimura, Arata*; Muroga, Takeo*; Takeuchi, Takao*; Nishitani, Takeo; Morioka, Atsuhiko
Fusion Engineering and Design, 81(8-14), p.1675 - 1681, 2006/02
Times Cited Count：3 Percentile：23.25(Nuclear Science & Technology)In a fusion reactor plant, a neutral beam injector (NBI) will be operated for a long time, and it will allow neutron streaming from NBI ports to outside of the plasma vacuum vessel. It requires the superconducting magnet to develop nuclear technology to produce stable magnetic field and to reduce activation of the magnet components. In this report, the back ground of the necessity and the contents of the nuclear technology of the superconducting magnets for fusion application are discussed and some typical investigation results are presented, which are the neutron irradiation effect on Nb
Sn wire, the development of low activation superconducting wire, and the design concept to reduce nuclear heating and nuclear transformation by streaming. In addition, recent activities in high energy particle physics are introduced and potential ripple effect of the technology of the superconducting magnets is described briefly.
Mori, Masahiro; ITER Japanese Participant Team
Fusion Engineering and Design, 81(1-7), p.69 - 77, 2006/02
Times Cited Count：1 Percentile：9.46(Nuclear Science & Technology)The ITER Transitional Arrangements (ITA) are conducted by the International Team with supports from participant teams (PTs). The Japanese PT (JA-PT) set up in JAERI has contributed to ITA by sharing a lot of technical tasks to verify feasibilities of fabrication and quality control method in procuring ITER equipments and facilities. For examples, trial fabrications of Nb3Sn strands have been performed by JA-PT with four potential suppliers, and one of the strand which meet the ITER requirements in all key parameters have already been chosen for one of the suppliers. All strands including the other suppliers strands will be fully qualified by the end of 2005. The trial fabrications of CS jackets and material for TF coil structure are also in progress at industrial level. Fabrication of the partial mock-ups of the vacuum vessel is also ongoing. Furthermore, JA-PT has made several technical developments on NB and EC systems to improve reliability of long pulse operations. Completing these technical preparations will make it possible to finalize the specification of ITER procurements.
Naka Fusion Research Establishment
JAERI-Review 2005-046, 113 Pages, 2005/09
JAERI-Review-2005-046.pdf:24.35MB
This annual report provides an overview of research and development activities at Naka Fusion Research Establishment, including those performed in collaboration with other research establishments of JAERI, research institutes, and universities, during the period from 1 April, 2004 to 31 March, 2005. The activities in the Naka Fusion Research Establishment are highlighted by researches in JT-60 and JFT-2M, theoretical and analytical plasma researches, research and development of fusion reactor technologies towards ITER and fusion power demonstration plants, and activities in support of ITER design and construction.
Naka Fusion Research Establishment
JAERI-Review 2004-023, 126 Pages, 2004/11
JAERI-Review-2004-023.pdf:28.0MB
no abstracts in English
Naka Fusion Research Establishment
JAERI-Review 2003-035, 129 Pages, 2003/11
JAERI-Review-2003-035.pdf:13.55MB
This annual report provides an overview of research and development (R&D) activities at Naka Fusion Research Establishment in collaboration with other research establishment of JAERI, research institutes, and universities during the period from 1 April, 2002 to 31 March, 2003. The activities in the Naka Fusion Research Establishment are highlighted by high performance plasma researches in JT-60 and JFT-2M, R&D of fusion reactor technologies towards ITER and fusion power demonstration plants, and activities in support of ITER design and construction.
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.
Seki, Masahiro; Yamanishi, Toshihiko; Shu, Wataru; Nishi, Masataka; Hatano, Toshihisa; Akiba, Masato; Takeuchi, Hiroshi; Nakamura, Kazuyuki; Sugimoto, Masayoshi; Shiba, Kiyoyuki; et al.
Fusion Science and Technology, 42(1), p.50 - 61, 2002/07
Times Cited Count：5 Percentile：33.55(Nuclear Science & Technology)Latest status on development of long-term fusion nuclear technologies at JAERI is overviewed. A tritium processing system for the ITER and DEMO reactors was designed and basic technologies for each component of this system was demonstrated successfully by an operation of the integrated system for one month. An ultra-violet laser with a wave length of 193 nm was found quite effective for removing tritium from in-vessel components of D-T fusion reactors. Blanket technologies have been developed for the Test Blanket Module of the ITER and for advanced blankets for DEMO reactors. This blanket is composed of Li
TiO breeder pebbles and neutron multiplier Be pebbles, contained in a box structures made of a reduced activation ferritic steel F82H. Mechanical properties of F82H under neutron irradiation up to 50 dpa were obtained in a temperature range from 200 to 500
C. Design of the International Fusion Materials Irradiation Facility (IFMIF) has been developed so as to obtain engineering data for candidate materials for DEMO reactors, under neutron irradiation up to 100-200 dpa.
IFMIF International Team
JAERI-Tech 2002-022, 97 Pages, 2002/03
JAERI-Tech-2002-022.pdf:9.17MB
Activities of International Fusion Materials Irradiation Facility (IFMIF) have been performed under an IEA collaboration since 1995. IFMIF is an accelerator- based deuteron (D+)-lithium (Li) neutron source designed to produce an intense neutron field (2 MW/m, 20 dpa/year for Fe) in a volume of 500 cm for testing candidate fusion materials. In 2000, a 3year Key Element technology Phase (KEP) of IFMIF was started to reduce the key technology risk factors. This interim report summarizes the KEP activities until mid 2001 in the major project work-breakdown areas of accelerator, target, test cell and design integration.
Nishi, Masataka; Hayashi, Takumi; Shu, Wataru; Nakamura, Hirofumi; Kawamura, Yoshinori; Yamada, Masayuki; Suzuki, Takumi; Iwai, Yasunori; Kobayashi, Kazuhiro; Isobe, Kanetsugu; et al.
Materialovedenie (Russian Science of Materials) No.2, p.42 - 45, 2002/00
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
Naka Fusion Research Establishment
JAERI-Review 94-011, 118 Pages, 1995/01
JAERI-Review-94-011.pdf:5.84MB
no abstracts in English
Seki, Yasushi; ;
Nihon Genshiryoku Gakkai-Shi, 37(3), 206 Pages, 1995/00
no abstracts in English
Seki, Yasushi
Purazuma, Kaku Yugo Gakkai-Shi, 70(12), 1318 Pages, 1994/12
no abstracts in English
Seki, Yasushi
Fusion Engineering and Design, 25, p.49 - 66, 1994/00
Times Cited Count：2 Percentile：27.65(Nuclear Science & Technology)no abstracts in English
Tsuji, Hiroshi
Enerugi, 26(3), p.80 - 84, 1993/03
no abstracts in English
Moriyama, Shinichi; ; Fujii, Tsuneyuki; ; ; Terakado, Masayuki; Kimura, Haruyuki; Saigusa, Mikio; Nagashima, Takashi; Ota, Mitsuru; et al.
Fusion Engineering and Design, 19, p.41 - 52, 1992/00
Times Cited Count：11 Percentile：69.75(Nuclear Science & Technology)no abstracts in English
Naruse, Yuji; Okuno, Kenji; Yoshida, Hiroshi; Konishi, Satoshi; Anderson, J. L.*; Bartlit, J. R.*
Journal of Nuclear Science and Technology, 27(12), p.1081 - 1095, 1990/12
no abstracts in English
Mori, Seiji*; ; Seki, Yasushi; Seki, Masahiro
FAPIG, 0(124), p.2 - 11, 1990/03
no abstracts in English
Okuno, Kenji; Enoeda, Mikio; ; ; Yoshida, Hiroshi; Naruse, Yuji; Anderson, J. L.*; Bartlit, J. R.*; Sherman, R. H.*; R.V.Carlson*; et al.
JAERI-M 90-028, 73 Pages, 1990/02
no abstracts in English
