Research reports progress on HTGR fuels and materials, indicating future collaboration efforts.
Japan Atomic Energy Agency (JAEA) and the Institute of Nuclear Physics (INP) have been being developing the High Temperature Gas-cooled Reactor (HTGR) fuels and materials by using WWR-K reactor within the framework of International Science and Technology Center (ISTC) since 2010 and so far. This paper reports the history, and the future plan. The cooperation was conducted via four ISTC project, K-1797, K-2222, KZ-2514 regular projects and K-2080p partner project, respectively for irradiation test for High burnup HTGR fuel, R&D on oxidation resistance graphite, Post Irradiation Experiment (PIE) for high burn-up HTGR fuel, R&D on SiC matrix HTGR fuel and, we are planning new open call ISTC project to observe Pd-SiC corrosion, now. Furthermore, JAEA determined a fuel R&D roadmap. According to the roadmap, JAEA starts the R&D, and WWR-K reactor is one of the candidates for the irradiation tests besides the ISTC projects. JAEA expects cooperation with INP in the future too.
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