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Title: Advanced Triso fuels with zirconium carbide for high temperature reactors

Conference ·
OSTI ID:20979515
;  [1]; ;  [2]
  1. University of South Carolina, Mechanical Engineering Department, 300 Main Street, Columbia, SC 29208 (United States)
  2. Nuclear Fuel Services, Inc., Erwin, TN 37604 (United States)

There are several options for the advanced TRISO fuel: one is primarily replacement SiC with ZrC and the other is a concept involving a thin ZrC layer coating on the kernel, which is then enclosed in usual TRISO coatings. An effort at modeling, fabrication and testing of an advanced TRISO coated UO{sub 2} fuel particle design incorporating an added layer of ZrC over the fuel kernel is under investigation. The objectives of the coated particle development program are to define the essentials of a production route for the manufacture of kernels and coated particles and to identify the important process parameters that determine the particle properties. Still, the integrity of the ZrC coating is important, but not the main goal. The primary purpose of a ZrC coating examination in this study is to determine hot it serves as an oxygen getter to limit CO production and hence pressure buildup that would stress coatings leading to failure. This additional ZrC coating also aids in retaining fission products within the kernel, and carbon diffusion in the particle is limited hence kernel migration rates are slowed. The combined result being that failure rates of coated particles should decrease. (authors)

Research Organization:
American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
OSTI ID:
20979515
Resource Relation:
Conference: Advanced nuclear fuel cycles and systems (GLOBAL 2007), Boise - Idaho (United States), 9-13 Sep 2007; Other Information: Country of input: France; 15 refs; Related Information: In: Proceedings of GLOBAL 2007 conference on advanced nuclear fuel cycles and systems, 1873 pages.
Country of Publication:
United States
Language:
English