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Two-Group Analysis of Thermal, One-Dimensional, Multi-Region Spherical Reactors
This technical report described the formulation of a set of two-group neutron diffusion equations and the solution for the critical fuel cross section in a one-dimensional, multi-region spherical reactor. A subsequent report will describe the ORACLE code developed for survey calculations using this method.
Date:
May 1, 1957
Creator:
Nestor, C. W.
System:
The UNT Digital Library