2 Matching Results
Results open in a new window/tab.
Results:
1 - 2 of
2
The Improvement of the Vertical Dispersion Matching of the Beam Transport Line Between AGS and RHIC
None
Date:
June 13, 1990
Creator:
J., Xu
Object Type:
Report
System:
The UNT Digital Library
Method of calculating test leakage rate for a spent fuel cask
This report presents a method for calculating containment test leakage rates of radionuclides from an example spent fuel cask. Three releasable radioactive sources are considered: residual contamination in the cask cavity, crud on the fuel elements, and the radionuclides within the fuel rods. The ANSI N14.5 standard is used to calculate the test leakage rates from the maximum permissible releases determined from 10 CFR 71 containment requirements. 6 refs., 2 tabs.
Date:
June 13, 1990
Creator:
Fischer, L. E.
Object Type:
Article
System:
The UNT Digital Library