Conceptual Design of New Polish High-Temperature Gas-Cooled Reactor (HTGR-POLA) Unveiled
The conceptual design of new Polish high-temperature gas-cooled reactor (HTGR-POLA) was presented for the first time in Poland. The design was developed by the by a team from the Department of Nuclear Energy & Environmental Analysis of National Center for Nuclear Research led by Dr. Mariusz Dabrowski. The conceptual design will also include safety analysis and tests of the reactor’s construction materials.
The presentation took place at a conference in Warsaw held on 12 June and organized by the Union of Entrepreneurs & Employers titled “SMR – Modular Atom for Business (Poland as an incubator of SMR technology in Europe?)”. The project was developed in cooperation with the Japan Atomic Energy Agency (JAEA), which operates the High-Temperature Test Reactor (HTTR).
Thee helium-cooled reactor will provide 30 MW of thermal power and helium temperature at the reactor outlet will be 750°C, at the inlet 325°C.
The helium-cooled reactor will feature a prismatic-type core comprising hexagonal blocks. The reactor will use TRISO-type fuel with 8-12% enrichment moderated by with graphite. The primary forced circulation helium cooling circuit will operate at a pressure of 6 MPa. It will feature passive and active safety systems, with a planned design life of 60 years.
According to the National Center for Nuclear Research, HTGR-POLA can be used for cogeneration with maximum gross electrical power of 10 MWe-year and high-temperature steam with a temperature of more than 540°C. Also, it can be used for industrial processes or for municipal heating.
World Nuclear News