Protection of nuclear graphite toward fluoride molten salt by glassy carbon deposit-Reference-Cited by-同舟云学术

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Protection of nuclear graphite toward fluoride molten salt by glassy carbon deposit

Published:2009-02 Issue:3 Volume:384 Page:292-302
ISSN:0022-3115
Container-title:Journal of Nuclear Materials
language:en
Short-container-title:Journal of Nuclear Materials

Author:

Bernardet V.,Gomes S.,Delpeux S.,Dubois M.,Guérin K.,Avignant D.,Renaudin G.,Duclaux L.

Publisher

Elsevier BV

Subject

Nuclear Energy and Engineering,General Materials Science,Nuclear and High Energy Physics

Reference24 articles.

1. The thorium molten salt reactor: Moving on from the MSBR

2. Chemistry and technology of Molten Salt Reactors – history and perspectives

3. Non-proliferation attributes of molten salt reactors

4. L.L. Korb, P.A. Waitkus, Vitreous carbon and process for preparation thereof, US Patent 4550,015, 29 October 1985.

5. Determining the shortest production time for glassy carbon ware

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