AGC-1 Experiment and Final Preliminary Design Report.

Bratton, R. ; Burchell, T.

Technical Information Center Oak Ridge Tennessee

关键词: AGR type reactors;    Design;    Graphite;    Creep;    Physical radiation effects;   

RP-ID  :  DE2007911565

学科分类：工程和技术（综合）

美国|英语

来源: National Technical Reports 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 degrees C and a peak irradiation dose of 5.8 x 10(sup 21) n/cm2 (E > 0.1 MeV), or 4.2 displacements per atom.