Research on the Assessment Method of Graphite Dust Generation in High-Temperature Gas-Cooled Reactor
摘要
The interaction between spherical fuel elements and graphite components in pebble-bed high-temperature gas-cooled reactors (PBHTGR) inevitably leads to the generation of graphite dust. Mechanical wear caused by the movement of graphite components is identified as the primary source of graphite dust. This dust is initially generated in the core region, feed pipes, or discharge pipes. A portion of the dust is carried by helium out of the core into the fuel handling system, subsequently flowing through hot gas ducts, evaporators, and the main helium blower. This study analyzed the temperature, load, and moving distance conditions during graphite component wear in PBHTGRs. By comparing experimental data on fuel element wear rates from existing literature, the annual graphite dust generation in PBHTGRs is conservatively estimated to be 20.52 kg/(year reactor).