AFIP-6 Characterization Summary Report

Keiser, Dr. Dennis D.

Idaho National Laboratory

关键词: Irradiation;    Afip-6;    Rertr;    Afip-6 Characterization Report;    11 Nuclear Fuel Cycle And Fuel Materials;   

DOI  :  10.2172/1033920
RP-ID  :  INL/EXT-11-21090
RP-ID  :  DE-AC07-05ID14517
RP-ID  :  1033920

美国|英语

来源: UNT Digital Library

【 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.