MOLTEN NUCLEAR FUEL SALTS AND RELATED SYSTEMS AND METHODS

摘要

This disclosure describes nuclear fuel salts usable in certain molten salt reactor designs and related systems and methods. Binary, ternary and quaternary chloride fuel salts of uranium, as well as other fissionable elements, are described. In addition, fuel salts of UClxFy are disclosed as well as bromide fuel salts. This disclosure also presents methods and systems for manufacturing such fuel salts, for creating salts that reduce corrosion of the reactor components and for creating fuel salts that are not suitable for weapons applications.

主权项

1. A nuclear reactor facility for generating power from a nuclear reaction, the reactor facility comprising:
a reactor core containing a fissionable fuel salt, the fissionable fuel salt having at least 5% by molar fraction UCl4 and wherein the fuel salt has a melting point of less than 600° C.; and a heat exchanger adapted to transfer heat from the fuel salt to a coolant.