Concrete Shield Performance of the VSC-17 Spent Nuclear Fuel Cask (Preprint).

Morton, S. L. ; Winston, P. L. ; Saegusa, T. ; Shirai, K. ; Sasahara, A.

Technical Information Center Oak Ridge Tennessee

关键词: Spent fuel casks;    Concretes;    Nuclear fuels;    Shielding;    Performance;   

RP-ID  :  DE2008911714

学科分类：工程和技术（综合）

美国|英语

来源: National Technical Reports Library

【 摘 要 】

The VSC-17 Spent Nuclear Fuel Storage Cask was surveyed for degradation of the concrete shield by radiation measurement, temperature measurement, and ultrasonic testing. No general loss of shielding function was identified.