Test plan using HTTR (High Temperature engineering Test Reactor)

Takada, Shoji; Iigaki, Kazuhiko ; Shinohara, Masanori ; Tochio, Daisuke ; Shimazaki, Yosuke ; Ono, Masato ; Nishihara, Tetsuo ; Fukaya, Yuji   ; Goto, Minoru  ; Tachibana, Yukio ; Sawa, Kazuhiro

JAEA has carried out research and development to establish the technical basis of HTGRs using HTTR. LOFC test to verify the inherent safety of HTGR under the condition of loss of forced cooling while the reactor shut-down system disabled was initiated. A temperature coefficient of reactivity is one of the important parameters for core dynamics calculations for safety analysis, and changes with burnup because of variance of fuel compositions, which has been measured to confirm the validity of the calculated ones. In order to connect hydrogen production system to HTTR, it is necessary to ensure the reactor safety when thermal-load of the hydrogen production system is lost. Thermal load fluctuation test is planned to demonstrate the reactor safety and gain the test data for validation of the plant dynamics code. It will be confirmed that the reactor become stable state during a part of removed heat at HTTR heat-sink is lost.