AGC-1 Experiment and Final Preliminary Design Report

Bratton, Robert L. ; Burchell, Tim

Idaho National Laboratory

关键词: Safety Reports;    Irradiation;    11 - Nuclear Fuel Cycle And Fuel Materials , 12 - Mgmt Of Radioactive And Non-Radioactive Wastes From Nuclear Facilities;    Graphite;    Physical Properties;   

DOI  :  10.2172/911565
RP-ID  :  INL/EXT-05-00622
RP-ID  :  DE-AC07-99ID-13727
RP-ID  :  911565

美国|英语

来源: UNT Digital Library

【 摘 要 】

This report details the experimental plan and design as of the preliminary design review for the Advanced Test Reactor Graphite Creep-1 graphite compressive creep capsule. The capsule will contain five graphite grades that will be irradiated in the Advanced Test Reactor at the Idaho National Laboratory to determine the irradiation induced creep constants. Seven other grades of graphite will be irradiated to determine irradiated physical properties. The capsule will have an irradiation temperature of 900 C and a peak irradiation dose of 5.8 x 10{sup 21} n/cm{sup 2} [E > 0.1 MeV], or 4.2 displacements per atom.