Thermal Shock Resistances and the Irradiation Effects ot Graphites and C/C-Composites for Fusion Reactor Devices
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概要
- 論文の詳細を見る
Graphites and/or C/C-composites as plasma-facing first wall components for fusion reactor devices are subjected occasionally to plasma disruption. Therefore the thermal shock resistances and fracture toughnesses of these materials must be evaluated to assure appropriate performances. In this study, the thermal shock resistance and fracture toughness of several kinds of graphites and C/C-composites for candidate first wall component tiles are evaluated. The mechanical and fracture mechanics properties for these specimens are also measured. Then, two graphites and three C/C-composites are irradiated with 1.1-1.9×10^<21>n/cm^2 (Energy>29fJ) at 650-1000℃ in a fission reactor (Japan Material Testing Reactor, JMTR) and the degradations in the thermal shock resistances and fracture toughnesses and the changes of mechanical and fracture mechanics properties due to the neutron irradiation are quantitatively studied.
- 東北大学の論文
- 1991-03-05
著者
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Sato S
Department Of Physics Nagoya University
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KURUMADA Akira
Faculty of Engineering, Ibaraki University
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Ishida Ryohei
Dep. Of Mech. Eng. Faculty Of Eng. Univ. Of Osaka Prefecture
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Sato Sennosuke
Dep. of Mech. Eng., Faculty of Eng., Ibaraki University
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Kurumada Akira
Dep. of Mech. Eng., Faculty of Eng., Ibaraki University
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Kawamata Kiyohiro
Dep. of Mech. Eng., Faculty of Eng., Ibaraki University
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Kurumada Akira
Faculty Of Engineering Ibaraki University
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Sato S
Inoue Superliquid Glass Project Exploratory Research For Advanced Technology Japan Science And Techn
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Kawamata Kiyohiro
Faculty Of Engineering Ibaraki University
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