Research and development on HTGR fuels and materials utilising WWR-K research reactor

Ueta, Shohei ; Asset, S.*; Tachibana, Yukio ; Fukaya, Yuji ; Gizatulin, S.*; Sakaba, Nariaki

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. In this presentation, R&D in the ISTC Projects, K-1797 regular project, K-2222 regular project, KZ-2514 regular project, and K-2080p partner project are explained. Moreover, future subjects which JAEA is planning to develop are also explained.

Language	:	English
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Meeting title	:	V International Scientific Forum "Nuclear Science and Technologies"
Held date	:	2024/10
Location (city)	:	Almaty
Location (country)	:	Kazakhstan
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Registration No. : BB20241175
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