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AFIP-3 Irradiation Summary Report [electronic resource].

Published
Washington, D.C. : United States. Office of the Assistant Secretary for Nuclear Energy, 2011.
Oak Ridge, Tenn. : Distributed by the Office of Scientific and Technical Information, U.S. Dept. of Energy.
Additional Creators
Idaho National Laboratory, United States. Office of the Assistant Secretary for Nuclear Energy, and United States. Department of Energy. Office of Scientific and Technical Information
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Summary
The Advanced Test Reactor (ATR) Full size plate In center flux trap Position (AFIP) experiment AFIP-3 was designed to evaluate the performance of monolithic fuels at a prototypic scale of 2.25 inches x 21.5 inches x 0.050 inches (5.75 cm x 54.6 cm x 0.13cm). The AFIP-3 experiment was fabricated by hot isostatic pressing (HIP) and consists of two plates, one with a zirconium (Zr) diffusion barrier and one with a silicon (Si) enhanced fuel/clad interface1,2. The following report summarizes the life of the AFIP-3 experiment through end of irradiation, including a brief description of the safety analysis, as-run neutronic analysis results, hydraulic testing results, and thermal analysis results.
Report Numbers
E 1.99:inl/ext-11-21776
inl/ext-11-21776
Subject(s)
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Note
Published through SciTech Connect.
04/01/2011.
"inl/ext-11-21776"
Danielle M Perez.
Funding Information
DE-AC07-05ID14517
View MARC record | catkey: 14662473