Materials for Molten-Salt Reactors
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
Operating with experience with the Molten-Salt Reactor Experiment (MSRE) has demonstrated the excellent compatibility of the graphite-Hastelloy N-flouride 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, (1) Hastelloy N with improved resistance to embrittlement by thermal neutrons, (2) graphite with better dimensional stability in a fast neutron flux, (3) graphite that is sealed to obtain a surface permeability of less than 10 to the -8 power cm square per second, and (4) a secondary coolant that is inexpensive and has a melting point of about 400°C. A brief description is given of the materials work in progress to satisfy each of these requirements. Our studies presently indicate that significant improvements can likely be accomplished in each area.
- Research Organization:
- Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
- Sponsoring Organization:
- US Atomic Energy Commission (AEC)
- DOE Contract Number:
- W-7405-ENG-26
- OSTI ID:
- 1457693
- Report Number(s):
- ORNL-TM--2511
- Country of Publication:
- United States
- Language:
- English
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