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- W2409005087 abstract "The Advanced Test Reactor (ATR) Full size plate In center flux trap Position (AFIP) experiment AFIP-4 was designed to evaluate the performance of monolithic uranium-molybdenum (U-Mo) fuels at a scale prototypic of research reactor fuel plates. The AFIP-4 test further examine the fuel/clad interface and its behavior under extreme conditions. After irradiation, fission gas retention measurements will be performed during post irradiation (PIE). The following report summarizes the life of the AFIP-4 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." @default.
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- W2409005087 date "2011-09-01" @default.
- W2409005087 modified "2023-09-23" @default.
- W2409005087 title "AFIP-4 Irradiation Summary Report" @default.
- W2409005087 doi "https://doi.org/10.2172/1027915" @default.
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