AFIP-6 Fabrication Summary Report

Moore, Glenn A. ; Marshall, M. Craig

Idaho National Laboratory

关键词: Plate;    Test Reactors Fabrication;    Monolithic;    11 Nuclear Fuel Cycle And Fuel Materials;    Performance;   

DOI  :  10.2172/1033877
RP-ID  :  INL/EXT-11-21655
RP-ID  :  DE-AC07-05ID14517
RP-ID  :  1033877

美国|英语

来源: UNT Digital Library

【 摘 要 】

The AFIP-6 (ATR Full-size plate In center flux trap Position) experiment was designed to evaluate the performance of monolithic fuels at a scale prototypic of research reactor fuel plates. Two qualified fueled plates were fabricated for the AFIP-6 experiment; to be irradiated in the INL Advanced Test Reactor (ATR). This report provides details of the fuel fabrication efforts, including material selection, fabrication processes, and fuel plate qualification.