Overview of Recent Japanese Activities and Plans in Fusion Technology

References

• V. CHUYANOV, ITER International Team, “Interface of Blanket Testing and ITER Design,” Fusion Science & Technol., 47, 469, (2005).
   Web of Science ®Google Scholar
• H. TAKATSU, et. al., “The role of IFMIF in the roadmap towards fusion power system,” to be published in J. Nucl. Mater.
   Google Scholar
• K. OKUNO, “Progress in the superconducting magnet technology through the ITER CS Model Coil programme,” IEEE Trans. ASC, 14, 1376 (2004).
   Google Scholar
• N. MITCHELL, “Summary, Assessment and Implications of the ITER Model Coils Test Results,” Fusion Eng. Des., 66 – 68, 971 (2003).
   Web of Science ®Google Scholar
• Y. NUNOYA, et al, “Experimental investigation on the effect of transverse electromagnetic force on the V-T curve of the CIC conductor,” IEEE Trans. ASC, 14, 1468 (2004).
   Google Scholar
• K. OKUNO, et al, “From CS and TF Model Coils to ITER: Lessons Learnt and Further Progress,” IEEE Trans. ASC, 16, 880 (2006).
   Google Scholar
• K. ABE, et al, “Manufacturing study and trail fabrication of radial plate for ITER toroidal field coil,” IEEE Trans. ASC, 16, 807 (2006).
   Google Scholar
• H. NAKAJIMA, et al, “New Cryogenic Material and Design for ITER Superconducting Magnet System,” Proc. 10th International Conference on Nuclear Engineering, ICONE10-22674, 2002, p.1.
   Google Scholar
• K. HAMADA, et al, “Demonstration of full scale JJ1 and 316LN fabrication for ITER TF coil structure,” presented at 24th Symposium of Fusion Technology, Warsaw, 2006.
   Google Scholar
• T. MITO, et. al., “Development and Operation of Superconducting System for LHD,” Proc. of 19th Symposium on Fusion Engineering (SOFE), p.144 (2002).
   Google Scholar
• S. IMAGAWA, et al, “Performance of the Helical Coils for the Large Helical Device in Six Years Operation,” IEEE Transaction on Applied Superconductivity, 14, 1388 (2004).
   Web of Science ®Google Scholar
• T. MITO et. al., “Applied superconductivity and cryogenic research activities in NIFS,” Fusion Eng. Des., (2006) (in press).
   Google Scholar
• K. SAKAMOTO, et. al., “Development of Long Pulse and High Power 170 Ghz Gyrotron,” J. Phys. Conf. Series. 25, 8 (2005).
   Google Scholar
• K. SAKAMOTO, et. al., “Development of the 170 GHz Gyrotron and Equatorial Launcher for ITER,” Proc. 21st IAEA Fusion Energy Conference, Chengdu, China, 2006, IAEA (2006).
   Google Scholar
• T. MUTOH, et. al., Physics of Plasmas 13, 056118 (2006) DOI: 10.1063/1.2177204
   Google Scholar
• R. KUMAZAWA, et. al., Nucl. Fusion, 46, S13 (2006).
   Web of Science ®Google Scholar
• T. INOUE, et. al., “R&D on a Hhigh Energy Accelerator and a Large Negative Ion Source for ITER,” Nucl. Fusion, 45, 790 (2005).
   Web of Science ®Google Scholar
• M. HANADA, et. al., “Production of High Power and Large-Area Negative Ion Beams for ITE,” Proc. 21st IAEA Fusion Energy Conference, Chengdu, China, 2006, IAEA (2006).
   Google Scholar
• O. KANEKO, et. al., “Status of Negative-Ion-Based neutral Beam Injectors in LHD”, Production and Neutralization of Negative Ions and Beams, (Proc. Int. Conf., Kiev, 2004), AIP Conference Proceedings 763, New York, 2005.
   Google Scholar
• M. ENOEDA, et al, “Overview of design and R&D of test blankets in Japan,” Fusion Eng. Des., 81, 415 (2006).
   Web of Science ®Google Scholar
• Y. NOMOTO, et. al., “Structural Concept of Japanese Solid Breeder Test Blanket Modules for ITER,” Fusion Eng. Des., 81, 719 (2006).
   Web of Science ®Google Scholar
• S. SATO, et. al., “Progress in the blanket neutronics experiments at JAERI/FNS,” Fusion Eng. Des., 81, 1183 (2006).
   Web of Science ®Google Scholar
• D.A. PETTI, G.R. SMOLIK, M.F. SIMPSON et al, “JUPITER-II molten salt Flibe research: An update on tritium, mobilization and redox chemistry experiments,” Fuion. Eng. Des., 81, 1439 (2006).
   Web of Science ®Google Scholar
• M. SIMPSON, et. al., “Quantitative measurement of beryllium-controlled redox of hydrogen fluoride in molten Flibe,” Fusion Eng. Des., 81, 541 (2006).
   Web of Science ®Google Scholar
• M. HARA, al., “Interactions between molten Flibe and metallic Be,” Fusion Eng. Des., 81, 561 (2006).
   Web of Science ®Google Scholar
• R.A. ANDERL, et. al., “Deuterium/tritium behavior in Flibe and Flibe-facing materials,” J. Nucl. Mater., 329-333, 1327 (2004).
   Web of Science ®Google Scholar
• A. KLIX, A. SUZUKI and T. TERAI, Fusion Eng. Des., 81, 713 (2006).
   Web of Science ®Google Scholar
• S. FUKADA, Fusion Eng. Des., 81, 477 (2006).
   Web of Science ®Google Scholar
• G. SMOLIK, et. al., J. Nucl. Mater., 329-333, 1322 (2004).
   Web of Science ®Google Scholar
• T. SATO, et. al., “Heat Transfer for high Prandtl and high temperature molten salt flow in sphere-packed pipe,” The 17th ANS Topical Meeting on the Technology of Fusion Energy (TOFE17), 2006 (under contribution).
   Google Scholar
• K. YUKI, et. al., “Flow visualization and heat transfer characteristics for sphere-packed pipes”, 9^th AIAA/ASME Joint Thermophysics and Heat Transfer Conference, Tracking-no. 54264 (2006).
   Google Scholar
• T. MUROGA, et. al., “Advances in Development of Vanadium Alloys and MHD Insulator-Coatings,” presented at ICFRM-12, Santa Barbara, December 2005.
   Google Scholar
• Z. YAO, et. al., “In situ formation and chemical stability of Er2O3 coating on V–4Cr–4Ti in liquid lithium,” Fusion Eng. Des., 75-79, 1015 (2005).
   Web of Science ®Google Scholar
• T. TANAKA, et. al., “Evaluation of insulating property of ceramic materials for V/Li blanket system under fission reactor irradiation,” Fusion Eng. Des., 75-79, 933 (2005).
   Web of Science ®Google Scholar
• T. NAGASAKA, et. al., “Tensile property of low activation vanadium alloy after liquid lithium exposure,” Fusion Eng. Des., 81, 307 (2006).
   Web of Science ®Google Scholar
• S. KONISHI, “Socio-economic study of fusion energy at the Japan Atomic Energy Research Institute,” Fusion. Eng. Des., 69, 523 (2003).
   Web of Science ®Google Scholar
• K. KOBAYASHI et. al., “Studies on Behavior of Tritium in Components and Structure Materials of Tritium Confinement and Detritiation Systems of ITER”, Proc. 21st IAEA Fusion Energy Conference, Chengdu, China, 2006.
   Google Scholar
• M. ICHIMASA et. al., “Tritium Elimination System Using Tritium Gas Oxidizing Bacteria”, Fusion Sci. Technol., 48, 759 (2005).
   Web of Science ®Google Scholar
• T. ODA, et. al., “Dynamic observation of the behavior of 3 keV D2+ irradiated into Li2O using IR absorption spectroscopy,” J. Nucl. Mater., 346, 306 (2005).
   Web of Science ®Google Scholar
• M. OYAIZU, et. al., “Correlation between annihilation of radiation defects and tritium release in neutron-irradiated LiAlO2,” Fusion Sci. Tech., 48, 638 (2005).
   Web of Science ®Google Scholar
• T. KINJO, et. al., “Introduction of tritium transfer step at surface layer of breeder grain for modeling of tritium release behavior from solid breeder materials,” Fusion Eng. Des., 81, 573 (2006).
   Web of Science ®Google Scholar
• S. FUKADA, et. al., “Reaction rate of Be with Fluorine Ion for Flibe Redox Control,” presented at ICFRM-12, Santa BarBara, December 2005.
   Google Scholar
• Y. HIROHATA, et. al., “Hydrogen isotopes retention in JT-60U,” presented at PSI-17, Hefei, China, May 2006.
   Google Scholar
• K. KOBAYASHI, et. al., “Study for the behavior of tritiated water vapor on organic materials,” in this proceedings.
   Google Scholar
• Y. TORIKAI, et. al., “Absorption, Trapping and Release Behavior of Tritium in SS316,” presented at PSI-17, Hefei, China, May 2006.
   Google Scholar
• M. ICHIMASA, et. al., “Tritium elimination system using tritium gas oxidizing bacteria,” Fusion Sci. Tech., 48, 759 (2005).
   Web of Science ®Google Scholar
• S. NISHIO, et. al., “Tight Aspect Ratio Tokamak Power Reactor with Superconducting TF Coils,” Proc. the 19th IAEA Fusion Energy Conf., Lyon, 2002, IAEA (2002).
   Google Scholar
• R. HIWATARI, et. al., “Demonstration tokamak fusion power plant for early realization of net electric power generation,” Nucl. Fusion, 45, 96 (2005).
   Web of Science ®Google Scholar
• K. TOBITA, et. al., “Concept of compact low aspect ratio demo reactor, SlimCS,” Proc. 21st IAEA Fusion Energy Conference, Chengdu, China, 16-22 October, 2006, IAEA (2006).
   Google Scholar
• A. SAGARA et. al., Nuclear Fusion, 45, 258 (2005).
   Web of Science ®Google Scholar
• A. SAGARA et. al., “Optimization Studies on Conceptual Designs of LHD-type Reactor FFHR,” The 17th ANS Topical Meeting on the Technology of Fusion Energy (TOFE17), 2006 (under contribution).
   Google Scholar
• A. MOESLANG, et. al., “The IFMIF test facilities design,” Fusion Eng. Des., 81, 863 (2006).
   Web of Science ®Google Scholar
• H. KONDO, et. al., “Experimental study of lithium free-surface flow for IFMIF target design,” Fusion Eng. Des., 81, 687 (2006).
   Web of Science ®Google Scholar
• S. EBARA, et. al., “Feasibly study on cast-like IFMIF high flux test module,” Fusion Eng. Des., 81, 887 (2006).
   Web of Science ®Google Scholar
• S. HIRAKANE, et. al., “Control of nitrogen concentration in liquid lithium by iron-titanium alloy,” Fusion Eng. Des., 81, 665 (2006).
   Web of Science ®Google Scholar
• M. KINOSHITA, et. al., “Experimental study of tritium recovery from liquid lithium by yttrium,” Fusion Eng. Des., 81, 567 (2006).
   Web of Science ®Google Scholar
• H. ONO, et. al., “Specimen size effects on fracture toughness of JLF-1 reduced-activation ferritic steel,” J. Nucl. Mater., 329-333, 1117 (2004).
   Web of Science ®Google Scholar
• H. KURISHITA,et al., “Fracture toughness of JLF-1 by miniaturized 3-Point Bend Specimens with 3.3-7.0 mm Thickness,” Mater. Trans., 45, 936 (2004).
   Web of Science ®Google Scholar
• H. HAGIWARA, et. al., “Measurement of neutron emission spectra in Li(d,xn) reaction with thick and thin targets for 40-MeV Deuterons,” Fusion Sci. Technol., 48, 1320 (2005).
   Web of Science ®Google Scholar
• S. MATSUDA, “The EU-Japan Broader Approach Activities,” presented at 24th Symposium of Fusion Technology, Warsaw, 2006.
   Google Scholar