1970/02/01 by H.E. McCoy, R.L. Beatty, W. H. Cook +6 · 1 citation
Engineering · Materials Science · Physics and Astronomy · #Nuclear reactor physics and engineering #Graphite, nuclear technology, radiation studies #Nuclear Physics and Applications #Graphite #Molten salt reactor #Molten salt #Embrittlement #Materials science #Melting point #Coolant #Metallurgy #Nuclear engineering #Composite material #Mechanical engineering #Engineering
paper · doi:10.13182/nt70-a28622
openalex publication_date 1970/02/01 · openalex created_date 2025/10/10 · openalex updated_date 2026/07/28
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 ~400°C. A brief description is given of the materials work in progress to satisfy each of these requirements.