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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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