Preliminary Design of a Helical Coil Heat Exchanger for a Fluoride Salt-Cooled High-Temperature Test Reactor

摘要

The Fluoride salt-cooled High-temperature Reactor (FHR) combines the coated particle fuel and graphite moderator with a liquid fluoride salt as the primary coolant for electricity generation and process heat applications. Fluoride salts were studied extensively for the Molten Salt Reactor (MSR) from 1950s to 1970s, while only recently have these salts been considered to be used in the solid-fuel high-temperature reactors, namely, FHRs. The high volumetric heat capacity of these fluoride salts provides potential for a higher power density than the gas-cooled reactors and therefore for a compact reactor system. In addition, the FHR is designed to employ a fully passive decay heat removal system and can potentially adopt a high-efficiency nuclear air-Brayton combined power cycle, which possesses mature technology and capability of producing peak power.