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Report No.
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Characterization of 2D-C/C composite for application to in-core structure of Very High Temperature Reactor (VHTR)

Shibata, Taiju ; Sumita, Junya ; Kunimoto, Eiji; Sawa, Kazuhiro

Very High Temperature Reactor (VHTR) is an advanced high temperature gas-cooled nuclear reactor to provide high temperature helium gas about 950 $$^{circ}$$C to the reactor outlet. To enhance its performance, it is important to develop heat-resistant ceramics composite material in the core so as to increase the operating temperature. For the application of the 2D-C/C composite (CX-270G), neutron irradiation effects on the dimension and thermal conductivity were studied. Neutron irradiation test was carried out by JMTR at 600 $$^{circ}$$C to the fluence of 8.2$$times$$10$$^{24}$$ n/m$$^{2}$$ (E$$>$$1.0MeV) corresponding to 1.2 dpa. It was shown that the irradiation-induced shrinkage of plain-woven CX-270G expressed the same trend of 2D- random fiber composite. The neutron irradiation decreased thermal conductivity of CX-270G and it seemed to be recovered to some extent above 1200 $$^{circ}$$C. It is thought that the annealing effect on irradiation-induced defects in fiber direction affects the recovery.

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