[3F01-05] High Temperature Gas Reactor

[3F04] Preliminary Investigation of Innovative HTGR's Fuel to reduce Fuel Temperature

*Kentaro Nagatsuka¹, Hiroyuki Sato², Yoshiyuki Imai², Xing L. Yan² (1. Univ. of Tsukuba, 2. JAEA)

Keywords:HTGR, Convergent Channel, Numerical Simulation

High Temperature Gas-cooled Reactor (HTGR) has received great attention as an advanced nuclear reactor due to its inherent safety characteristics and high temperature heat supply capability. However, its core power density is presently limited in order to ensure containment performance of fission products within the fuel. This study investigates a potential method of increasing power density by enhancing the core heat transfer performance with the use of convergent flow channels. The thermal-hydraulics of fuel blocks of HTGR with them is analyzed by numerical simulation, and the effects of its dimensions on fuel temperature are shown.