Visualizing MCNP Tally Segment Geometry and Coupling Results with ABAQUS. 2007 ANS Winter Meeting.

Parry, J. R. ; Galbraith, J. A.

Technical Information Center Oak Ridge Tennessee

关键词: Graphite;    Irradiation;    Compliance;    Creep;    Dimensions;   

RP-ID  :  DE2008912910

学科分类：工程和技术（综合）

美国|英语

来源: National Technical Reports Library

【 摘 要 】

The Advanced Graphite Creep test, AGC-1, is planned for irradiation in the Advanced Test Reactor (ATR) in support of the Next Generation Nuclear Plant program. The experiment requires very detailed neutronics and thermal hydraulics analyses to show compliance with programmatic and ATR safety requirements. The MCNP model used for the neutronics analysis required hundreds of tally regions to provide the desired detail. A method for visualizing the hundreds of tally region geometries and the tally region results in 3 dimensions has been created to support the AGC-1 irradiation. Additionally, a method was created which would allow ABAQUS to access the results directly for the thermal analysis of the AGC-1 experiment.