2019 Fall Meeting

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Oral presentation

VI. Fusion Energy Engineering » 601-2 Fusion Reactor Material Science (Reactor and Blanket Materials, Irradiation Behavior)

[2L16-18] Neutron Multiplier/Shielding Materials

Thu. Sep 12, 2019 4:20 PM - 5:10 PM Room L (Common Education Bildg. 2F E22)

Chair:Takumi Chikada(Shizuoka Univ.)

4:50 PM - 5:05 PM

[2L18] Improvement of hydrogen release temperature of metal hydride neutron shielding material by Cr addition

*Masashi Sugatsuke1, Teruya Tanaka2, Yuji Ohishi1, Ken Kurosaki3, Hiroaki Muta1 (1. Osaka Univ., 2. NIFS, 3. Kyoto Univ.)

Keywords:Hydride, Neutron shielding material, Fusion reactor

While Zr hydride and Ti hydride show good neutron shielding ability, hydrogen release at high temperature is a major issue for safety. In this study, we attempted to improve the hydrogen release temperature of these metal hydrides by adding metal Cr. The results were compared to those of pure Zr hydride and Ti hydride to evaluate the effects of Cr addition.