Abstract:

NEW DEVELOPMENTS IN MATERIALS FOR MOLTEN-SALT REACTORS

Authors:

 H. E. McCOY, R. L. BEATTY, W. H. COOK, R. E. GEHLBACH, C. R.  KENNEDY, J.  W. KOGER, A. P. LITMAN, C. E. SESSIONS and J.  R. WEIR

Metals and Ceramics Division,  Oak Ridge National Laboratory

Oak Ridge, Tennessee 37830

October 10, 1969

Operating experience with the Molten-Salt Reactor Experiment (MSRE) has demonstrated the excellent compatibility of the graphite-Hastelloy N-fluoride salt system at 650°C. Several improvements in materials are needed for a molten-salt breeder reactor with a basic plant life of 30 years; specifically: Hastelloy-N with improved resistance to embrittlement by thermal neutrons; graphite with better dimensional stability in a fast neutron flux; graphite that is sealed to obtain a surface permeability of <10-8 cm2 /sec; and a secondary coolant that is inexpensive and has a melting point of ~4o0°C. A brief description is given of the materials work in progress to satisfy each of these requirements.

Dec 5, 2014   1304   egeneration    National Academy Of Sciences Technical Briefs
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