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Title: Ag Transport Through Non-Irradiated and Irradiated SiC

Silicon carbide is the main barrier to diffusion of fission products in the current design of TRistuctural ISOtropic (TRISO) coated fuel particles, and Ag is one of the few fission products that have been shown to escape through this barrier. Because the SiC coating in TRISO is exposed to radiation throughout the lifetime of the fuel, understanding of how radiation changes the transport of the fission products is essential for the safety of the reactor. The goals of this project are: (i) to determine whether observed variation in integral release measurements of Ag through SiC can be explained by differences in grain size and grain boundary (GB) types among the samples; (2) to identify the effects of irradiation on diffusion of Ag through SiC; (3) to discover phenomena responsible for significant solubility of Ag in polycrystalline SiC. To address these goals, we combined experimental analysis of SiC diffusion couples with modeling studies of diffusion mechanisms through bulk and GBs of this material. Comparison between results obtained for pristine and irradiated samples brings in insights into the effects of radiation on Ag transport.
Authors:
 [1] ;  [1] ;  [1]
  1. Univ. of Wisconsin, Madison, WI (United States)
Publication Date:
OSTI Identifier:
1242964
Report Number(s):
DOE/NEUP--11-2988
11-2988; TRN: US1600927
DOE Contract Number:
AC07-05ID14517
Resource Type:
Technical Report
Research Org:
University of Wisconsin, Madison, WI (United States)
Sponsoring Org:
USDOE Office of Nuclear Energy (NE)
Country of Publication:
United States
Language:
English
Subject:
36 MATERIALS SCIENCE; 11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS; 73 NUCLEAR PHYSICS AND RADIATION PHYSICS; SILICON CARBIDES; DIFFUSION; FISSION PRODUCTS; GRAIN BOUNDARIES; IRRADIATION; ATOM TRANSPORT; COATED FUEL PARTICLES; COMPARATIVE EVALUATIONS; GRAIN SIZE; POLYCRYSTALS; DESIGN; SOLUBILITY; VARIATIONS; SILVER; PHYSICAL RADIATION EFFECTS