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SM-1 Shielding Analyses
Abstract: This technical report analyzes gamma dose rate and neutron measurements in their relation to the SM-1 shield design and is a continuation of previous shielding measurements and analyses reported in APAE-35 and APAE-35 Supplement 2. The data reported herein are spent fuel element and rod drive pit gamma dose rates. An analysis of gamma dose rates off the core midplane is presented and compared with test data.
Date:
June 20, 1962
Creator:
Stephenson, L. D.
System:
The UNT Digital Library
Prediction of the Critical Heat Flux in Forced Convection Flow
From summary: "A superposition model is developed to predict the critical heat flux in forced convection flow. The model is applied to available experimental results in boiling water flows and good agreement is obtained between the model and test data over the multitude of geometries, flow rates, pressures, and fluid enthalpies tested to-date."
Date:
June 20, 1962
Creator:
Levy, S.
System:
The UNT Digital Library
Pilot Plant Development Studies of a Continuous Process for Recovering Uranium from Nichrome Fuels
Report documenting a process for recovering uranium from nichrome fuels (HTRE). This is accomplished by dissipating the fuel into a mixture of HCl-HNO3, stripping away chlorine ions with HN03, and recovering the uranium via tributyl phosphate solvent extraction.
Date:
June 20, 1962
Creator:
Chamberlain, H. V.
System:
The UNT Digital Library