AFIP-3 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: Summary Report;    Afip-3;    Irradiation;    11 Nuclear Fuel Cycle And Fuel Materials Afip-3;   

DOI  :  10.2172/1058080
RP-ID  :  INL/EXT-11-21776
RP-ID  :  DE-AC07-05ID14517
RP-ID  :  1058080

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-3 was designed to evaluate the performance of monolithic fuels at a prototypic scale of 2.25 inches x 21.5 inches x 0.050 inches (5.75 cm x 54.6 cm x 0.13cm). The AFIP-3 experiment was fabricated by hot isostatic pressing (HIP) and consists of two plates, one with a zirconium (Zr) diffusion barrier and one with a silicon (Si) enhanced fuel/clad interface1,2. The following report summarizes the life of the AFIP-3 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.