Description: Abstract: A fuel development program has been conducted, to investigate the behavior of U-10 wt% Mo alloy at the fission rates and temperatures anticipated in Core I of the Hallam Nuclear Power Facility.
Date: February 1, 1965
Creator: Willard, R. M. & Schmitt, A. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department