RERTR-7 Irradiation Summary Report

[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.

[发布日期] 2011-12-01

[学科分类] 核能源与工程

[关键词] BURNUP;ENRICHED URANIUM;FISSION;HEAT FLUX;HYDRAULICS;IRRADIATION;RESEARCH AND TEST REACTORS;TARGETS;TESTING RERTR