Zirconium Matrix Cermet for a Mixed Uranium-Thorium Oxide Fuel in an SBWR
Author:
Affiliation:
1. Purdue University, School of Nuclear Engineering 400 Central Drive, West Lafayette, Indiana 47907-2017
Publisher
Informa UK Limited
Subject
Condensed Matter Physics,Nuclear Energy and Engineering,Nuclear and High Energy Physics
Link
https://www.tandfonline.com/doi/pdf/10.13182/NT07-A3800
Reference11 articles.
1. Thorium dioxide: properties and nuclear applications
2. B. R. T. FROST, Nuclear Fuel Elements, p. 247, Pergamon Press, New York (1982).
3. Perspectives of the thorium fuel cycle
4. The Nonproliferative Light Water Thorium Reactor: A New Approach to Light Water Reactor Core Technology
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