Maritime Gas-Cooled Reactor Program: Suggested Values for the Partial Cross Sections of U²³⁵ for Use in the Neutronic Analysis of Thermal and Intermediate Reactors
Description: From abstract: In this report a consistent set of U-235 partial cross sections for use in the analysis of thermal or intermediate reactor systems has been provided.
Date: July 17, 1961
Creator: Goodjohn, A. J. & Wikner, N. F.
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Partner: UNT Libraries Government Documents Department