Studies on Components for a Molten Salt Reactor

Paper in proceedings (conference paper)

en

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.

2003-08-22

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

Brno

Proceedings of the International Symposium SMIRT 17

F537–

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