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184 results on '"Kurishita, H."'

42. Development of advanced high heat flux and plasma-facing materials

Author

Linsmeier, Ch., primary, Rieth, M., additional, Aktaa, J., additional, Chikada, T., additional, Hoffmann, A., additional, Hoffmann, J., additional, Houben, A., additional, Kurishita, H., additional, Jin, X., additional, Li, M., additional, Litnovsky, A., additional, Matsuo, S., additional, von Müller, A., additional, Nikolic, V., additional, Palacios, T., additional, Pippan, R., additional, Qu, D., additional, Reiser, J., additional, Riesch, J., additional, Shikama, T., additional, Stieglitz, R., additional, Weber, T., additional, Wurster, S., additional, You, J.-H., additional, and Zhou, Z., additional

Published
2017
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43. Impact Properties of TiC Dispersed Molybdenum Alloys Exposed to 2273 K Heating

Author

Kitsunai, Y., Kurishita, H., Kayano, H., Hiraoka, Y., Takida, T., and Igarashi, T.

Subjects
embrittlement, molybdenum, grain boundary, recrystallization, titanium carbide
Abstract

Ultra-fine grained molybdenum alloys with fine TiC particles at grain boundaries that were recently developed by the authors are very promising for the application to divertor components in advanced fusion devices. In order to examine the impact toughness and microstructural change of the alloys which were exposed to high temperature heating, miniaturized flat specimens, 1 mm by 1 mm by 20 mm, of both the alloys with TiC additions to 1.0 wt% and TZM alloy were subjected to vacuum heating up to 2273 K for 3.6 ks. The impact toughness was evaluated by three-point bending tests. It is shown that the developed alloys exhibit much improved toughness (lower ductile-to-brittle transition temperature and higher yield and maximum strengths) and the toughness increases both by increasing TiC content and by using mechanical alloying (MA) treatment for fabrication : the ductile-to-brittle transition temperature of the MA treated alloy with 1 wt% TiC is 75 K lower than that of TZM. In addition, the alloy with 1 wt% TiC shows no significant grain growth, though TEM observation indicate the occurrence of recrystallization.

Published
1997

44. Production of Helium in Iron by Proton Irradiation

Author

Konashi, K., Shibayama, T., Teshigawara, M., Kurishita, H., and Kayano, H.

Subjects
radiation damage, proton irradiation, computer simulation, Physics::Accelerator Physics
Abstract

The d-t fusion reactions produce neutron with energies up to 14.1MeV. These neutrons, in addition to producing atomic displacement damage, will induce nuclear transmutation reactions. In particular, helium will be generated at high rate in materials. Since helium is a potent agent in nucleating cavities, the mechanical properties of materials may be affected significantly. It is important, therefore, to determine experimentally the helium accumulation effect on radiation damage of materials under conditions similar to those in a fusion reactor. We indicated that proton beam experiments are a useful tool to study radiation damage by fast neutron in fusion reactor. Productions of both atomic displacement damage and helium in materials have been simulated by computer code. Energy deposition in target materials is also estimated to consider the heating problem. The transmutation calculations indicated that the proton beam experiments imitate satisfactorily the ratios of transmutation rates to displacement rates calculated for the first wall of fusion reactor. Constant concentration of accumulated helium can be achieved across the target thickness. Cooling of target of 1mm thickness could be handled without experimental difficulty in samples in the case of irradiation of 0.1mA/cm^2 proton beam.

Published
1997

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