Data Report on Post-Irradiation Dimensional Change of AGC-1 Samples

Windes, William

Idaho National Laboratory

关键词: Vhtr;    Post Irradiation Examination;    Agc-1 Graphite;    11 Nuclear Fuel Cycle And Fuel Materials Agc-1 Graphite;   

DOI  :  10.2172/1056006
RP-ID  :  INL/EXT-12-26255
RP-ID  :  DE-AC07-05ID14517
RP-ID  :  1056006

美国|英语

来源: UNT Digital Library

【 摘 要 】

This report summarizes the initial dimensional changes for loaded and unloaded AGC-1 samples. The dimensional change for all samples is presented as a function of dose. The data is further presented by graphite type and applied load levels to illustrate the differences between graphite forming processes and stress levels within the graphite components. While the three different loads placed on the samples have been verified [ ref: Larry Hull’s report] verification of the AGC-1 sample temperatures and dose levels are expected in the summer of 2012. Only estimated dose and temperature values for the samples are presented in this report to allow a partial analysis of the results.