Abstract
High Temperature Gas-cooled Reactor (HTGR) and Very High Temperature Reactor (VHTR) are attractive nuclear reactors to obtain high temperature helium gas at the reactor outlet. To enhance the thermal efficiency, the in-core internals of HTGR/VHTR, especially control rods, are subjected to the severe thermo-mechanical condition. The carbon-carbon (C/C) composite is one of the advanced material candidates for the control rod sheath of the advanced reactors where the excellent thermal resistance and stability are required because of the possible severe condition. The Research and development on the C/C composite application to HTGR have been carried out since 1990s. JAEA and Toyo Tanso have carried out the R & D on C/C composite to be used for control rod. Application of C/C composite is recently focused as one of the important subjects to develop VHTR in the international R & D activities. Scheme of the development in the JAEA/Toyo collaboration is outlined as follow: After the feasibility of C/C composite rod was demonstrated by a conceptual design, the procedure is progressing as follows; (1) Database establishment, (2) Design and manufacturing of components, and (3) Demonstration test by High Temperature engineering Test Reactor.
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