主催: The Japan Society of Mechanical Engineers
会議名: 第30回 原子力工学国際会議（ICONE30）
開催日: 2023/05/21 - 2023/05/26
HTGR has a potential to produce competitive and large amount of carbon-free hydrogen because of its capability to supply high temperature heat of nuclear energy. JAEA started a project of HTTR heat application test producing hydrogen with the HTTR to develop a massive, cost-effective and carbon-free hydrogen production technology utilizing a HTGR.
In present study, the safety design philosophy is developed for the HTTR heat application test facility connecting HTTR and the hydrogen production plant. The postulated events in HTTR heat application facility were identified to develop the safety design philosophy conforming to the requirements in the applicable laws and/or standards.
Considering the characteristics of HTTR heat application test facility, basic philosophy for the safety design was proposed to apply “Act on the Regulation of Nuclear Source Material, Nuclear Fuel Material and Reactors” for the nuclear reactor plant including the equipment with pressure boundary of secondary helium coolant. For the hydrogen production plant composed of systems for methane supply, product gas combustion and steam supply, “High Pressure Gas Safety Act” was applied to for ensuring high level protection against hazards of combustible gases. A demarcation boundary for applicable law is set on valves connecting the nuclear reactor plant and the hydrogen production plant.
The design philosophy of HTTR heat application test facility was proposed considering each identified postulated event including the internal fire, the tornado, the aircraft crash, the forest fire, the fire and explosion in adjacent facility and poisonous gas leak to conform safety requirements and standards. For example, the facility will be designed to protect the important safety systems against the internal fire by appropriate implementation of fire protection measures and by implementation of the offset distance and/or barrier against postulated explosion of leaked combustible gases from the SR.
