RERTR-6 Irradiation Summary Report

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

Idaho National Laboratory

关键词: Rertr-6;    Research And Test Reactors;    Irradiation;    Swelling;    Hydraulics;   

DOI  :  10.2172/1033908
RP-ID  :  INL/EXT-11-24282
RP-ID  :  DE-AC07-05ID14517
RP-ID  :  1033908

美国|英语

来源: UNT Digital Library

【 摘 要 】

The Reduced Enrichment for Research and Test Reactor (RERTR) experiment RERTR-6 was designed to evaluate several modified fuel designs that were proposed to address the possibility of breakaway swelling due to porosity within the (U. Mo) Al interaction product observed in the full-size plate tests performed in Russia and France1. The following report summarizes the life of the RERTR-6 experiment through end of irradiation, including as-run neutronic analyses, thermal analyses and hydraulic testing results.