Performance test of the HTTR (high temperature engineering test reactor )

摘要

The High Temperature Engineering Test Reactor (HTTR), which is the first High Temperature Gas-cooled Reactor (HTGR) in Japan, is a graphite-moderated and helium-cooled reactor with a thermal output of 30MW and a maximum outlet gas temperature of950°C and has the capability to demonstrate nuclear process heat utilization using an intermediate heat exchanger.The construction of the HTTR was decided by Japanese Atomic Energy Commission (JAEC) in 1987 and started in March 1991 by the Japan Atomic Energy Research Institute (JAERI) to establish and upgrade the technology basis for an HTGR also to serve as apotential tool for new and innovative basic research on high temperature technologies.The construction of the HTTR almost ended in 1996, and the pre-operation and the commissioning tests had been carried out from 1996 till 1998 before fuel was loaded in the core.Divided into four steps depending on the hazards and interfaces involved, the pre-operation and the commissioning tests were performed. It was confirmed from test results that HTTR plant system was capable of fuel loading.