600-MWe high-temperature gas-cooled reactor nuclear power plant HTR-PM600

The HTR-PM600 high-temperature gas-cooled reactor nuclear power plant is based on the technology of the high-temperature gas-cooled reactor pebble-bed module (HTR-PM) demonstration project. It utilizes proven HTR-PM reactor and steam generator modules with a thermal power of 250 MWth and power generation of approximately 100 MWe per module. Six modules in parallel, connected to a steam turbine, form a 600-MWe nuclear power plant. In addition, its system configuration in the nuclear island is identical to that of the HTR-PM in which the technical risks are minimized. Under this principle, the HTR-PM600 achieves the same level of inherent safety as the HTR-PM. The concept of a ventilated low-pressure containment (VLPC) is unchanged; however, a large circular VLPC accommodating all six reactor modules is adopted rather than the previous small-cavity-type VLPC, which contains only one module, as defined for the HTR-PM. The layout of the nuclear island and its associated systems refer to single-unit pressurized water reactor (PWR) practices. With this layout, the HTR-PM600 achieves a volume size of the nuclear island that is comparable to a domestic PWR of the same power level. This will be a Generation IV nuclear energy technology that is economically competitive.

Automated summary

The HTR-PM600 high-temperature gas-cooled reactor nuclear power plant is a nuclear power plant based on the technology of the high-temperature gas-cooled reactor pebble-bed module demonstration project. It utilizes six parallel reactor modules and a steam turbine to form a 600 MWe nuclear power plant. It provides the same level of inherent safety as the HTR-PM and has a similar system configuration, but with a larger containment to accommodate more modules.