Studies on Components for a Molten Salt Reactor

conference paper

English

The aim is contribute to a design of selected components of molten salt reactors with fuel in the molten fluoride salt matrix. Molten salt reactors permit the utilization of plutonium and minor actinides from a traditional nuclear power stations as new nuclear fuel with production of electricity. Results of preliminary feasibility studies of an intermediate heat exchanger, small power salt pump and a modular conception of steam generator for a demonstration unit of the MSR (30 MW) are summarized.

heat exchangers, molten fluoride salt, centrifigal pump, heat carriers, steam generator

NEJEDLÝ, M., MATAL, O.

22. 8. 2003

Ústav aplikované mechaniky, s. r. o., Brno

Brno

F537

8