RERTR-7 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: Heat Flux;    Research And Test Reactors;    Irradiation;    Fission;    Rertr;   

DOI  :  10.2172/1033909
RP-ID  :  INL/EXT-11-24283
RP-ID  :  DE-AC07-05ID14517
RP-ID  :  1033909

美国|英语

来源: UNT Digital Library

【 摘 要 】

The Reduced Enrichment for Research and Test Reactor (RERTR) experiment RERTR-7A, was designed to test several modified fuel designs to target fission densities representative of a peak low enriched uranium (LEU) burnup in excess of 90% U-235 at peak experiment power sufficient to generate a peak surface heat flux of approximately 300 W/cm2. The RERTR-7B experiment was designed as a high power test of 'second generation' dispersion fuels at peak experiment power sufficient to generate a surface heat flux on the order of 230 W/cm2.1 The following report summarizes the life of the RERTR-7A and RERTR-7B experiments through end of irradiation, including as-run neutronic analyses, thermal analyses and hydraulic testing results.