AFIP-6 Characterization Summary Report

[摘要] The AFIP-6 (ATR Full-size-plate In center flux trap Position) Characterization Summary Report outlines the fresh fuel characterization efforts performed during the AFIP-6 experiment. The AFIP-6 experiment was designed to evaluate the performance of monolithic uranium-molybdenum (U-Mo) fuels at a scale prototypic of Advanced Test Reactor (ATR) fuel plates (45-inches long). The AFIP-6 test was the first test with plates that were swaged into the rails of the assembly. This test served to examine the effects of a plate in a swaged condition with longer fuel zones (22.5-inches long), that were centered in the plate. AFIP-6 test plates employed a zirconium interlayer that was co-rolled with the fuel foil. Previous mini-plate and AFIP irradiation experiments performed in ATR have demonstrated the stable behavior of the interface between the U-Mo fuel and the zirconium interlayer.

[发布日期] 2011-12-01

[学科分类] 核能源与工程

[关键词] FUEL PLATES;IRRADIATION;PERFORMANCE;PLATES;TEST REACTORS;ZIRCONIUM AFIP-6;AFIP-6 characterization report;AFIP-6 characterization summary report;RERTR