AFIP-2 Irradiation Summary Report

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

关键词: DIFFUSION BARRIERS;    FRICTION;    HYDRAULICS;    IRRADIATION;    PERFORMANCE;    PLATES;    SAFETY;    SAFETY ANALYSIS;    SILICON;    TEST REACTORS;    TESTING;    THERMAL ANALYSIS;    ZIRCONIUM AFIP-2 Irradiation Summary Report;   

DOI  :  10.2172/1023477
RP-ID  :  INL/EXT-11-21599
PID  :  OSTI ID: 1023477
Others  :  TRN: US1104586

学科分类：核能源与工程

美国|英语

来源: SciTech Connect

【 摘 要 】

The Advanced Test Reactor (ATR) Full size plate In center flux trap Position (AFIP) experiment AFIP-2 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-2 experiment was fabricated by friction bond (FB) 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-2 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. The safety analyses performed for AFIP-2 are summarized in Table 5 of the following report.