New Developments in Materials for Molten-Salt Reactors
作者:
McCoyH. E.,
BeattyR. L.,
CookW. H.,
GehlbachR. E.,
KennedyC. R.,
KogerJ. W.,
LitmanA. P.,
SessionsC. E.,
WeirJ. R.,
期刊:
Nuclear Applications and Technology
(Taylor Available online 1970)
卷期:
Volume 8,
issue 2
页码: 156-169
ISSN:0550-3043
年代: 1970
DOI:10.13182/NT70-A28622
出版商: Taylor&Francis
数据来源: Taylor
摘要:
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<10−8cm2/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.
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