Pile Periods and the Inhour Equation Accounting for Delayed Neutron Groups from Fission of U²³⁵ and Pu²³⁹
Description:
Calculations are presented regarding the effect of delayed neutrons in reactors fueled with mixtures of Pu²³⁹ and U²³⁵. Results are plotted to illustrate the change in thermal flux as a function of time for various positive or negative step changes in reactivity.
Date:
April 27, 1956
Creator:
Astley, E. R.
Partner:
UNT Libraries Government Documents Department