AFIP-6 Irradiation Summary Report

Perez, Danielle M ; Lillo, M. A. ; Chang, G. S. ; Roth, G. A. ; Woolstenhulme, N. E. ; Wachs, D. M.

Idaho National Laboratory

关键词: Testing;    Irradiation;    Afip-6;    Hydraulics;    Safety Analysis;   

DOI  :  10.2172/1033886
RP-ID  :  INL/EXT-11-23296
RP-ID  :  DE-AC07-05ID14517
RP-ID  :  1033886

美国|英语

来源: UNT Digital Library

【 摘 要 】

The Advanced Test Reactor (ATR) Full size plate In center flux trap Position (AFIP) experiment AFIP-6 was designed to evaluate the performance of monolithic uranium-molybdenum (U-Mo) fuels at a length prototypic to that of the ATR fuel plates (45 inches in length). The AFIP-6 test was the first test with plates in a swaged condition with longer fuel zones of approximately 22.5 inches in length1,2. The following report summarizes the life of the AFIP-6 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.