Fabrication and preliminary evaluation of metal matrix microencapsulated fuels

Author:

Terrani Kurt A.,Kiggans Jim O.,Snead Lance L.

Publisher

Elsevier BV

Subject

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

Reference46 articles.

1. D.L. Hanson, A review of radionuclide release from HTGR cores during normal operation, EPRI Report 1009382, Electric Power Research Institute, February 2004.

2. J. Phillips, C. Barnes, J. Hunn, Fabrication and comparison of fuels for Advanced Gas Reactor irradiation tests, Proceedings of HTR 2010, Prague, Czech Republic, Oct 2010, paper 236.

3. J.D. Hunn, R.A. Lowden, Data compilation for AGR-1 baseline coated particle composite LEU01-46T, ORNL/TM-2006/019, Oak Ridge National Laboratory, Oak Ridge, TN, 2006.

4. Elliott S. Fray, James H. Miller, Brian C. Jolly, John D. Hunn, in preparation.

5. R.A. Lowden, J.C. McLaughlin, J.R. Kelley, Nitride ceramic coatings for gas-cooled fast reactor particle fuel, in: Proceedings of GLOBAL 2003, American Nuclear Society, New Orleans, Nov 16–20, 2003, p. 523.

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