Buildup of Fission Products in Reactor Fuel and Coolant With 'Unclad' Fuel Material
Description:
Concentrations of fission products in the fuel and in the coolant stream of a generalized reactor power plant employing unclad fuel material were calculated using actual fission-product chains and wide ranges of assumed values of escape rate from the fuel and removal rate from the coolant stream. The calculations were made on an IBM 704 digital computer. Some typical results are displayed in the form of graphs to illustrate the effects of the variables. As data on escape rates from fuel and rem…
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Date:
October 18, 1961
Creator:
Cottrell, W. B. & Mann, L. A.
Item Type:
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Report
Partner:
UNT Libraries Government Documents Department