The Action of Oxygen on Activated Charcoal (open access)

The Action of Oxygen on Activated Charcoal

The following report provides information conducted with the purpose of ascertaining the effect of oxygen on activated charcoal at approximately one atmosphere by measuring the amount of CO2 formed over a known length of time.
Date: June 29, 1951
Creator: Bigelow, J. E.; Belaga, M. W. & Mulvihill, R. J.
System: The UNT Digital Library
Stability of Split Hollow Cylinders (open access)

Stability of Split Hollow Cylinders

Abstract: "The behavior of radially split hollow cylinders upon heating is discussed."
Date: June 29, 1944
Creator: Karush, William & Monk, A. T.
System: The UNT Digital Library
A Problem in the Conversion of Neutron Dose to Flux (open access)

A Problem in the Conversion of Neutron Dose to Flux

This report discusses the calculation involved in converting neutron dose to flux. In order to test conversion calculation methods, the flux entering the Oak Ridge National Laboratory Lid Tank and the water by the north face of the Oak Ridge National Laboratory Bulk Shielding Reactor was used.
Date: June 29, 1953
Creator: McMillan, D. E.
System: The UNT Digital Library
Spectrographic Analysis of Plutonium by the Thenoyltrifloroacetone Extraction Method (open access)

Spectrographic Analysis of Plutonium by the Thenoyltrifloroacetone Extraction Method

Impurities are separated from plutonium solutions by means of TTA (thenoyltrifluoracetone) extractions. Plutonium in hydrochloric acid solution is reduced to the trivalent state with hydroxylamine, and some impurities are extracted into hezone or a solution of TTA in hezone. The organic phase is removed, and the plutonium in the aqueous phase is oxidized to the tetravalent state with nitric acid. Investigations of several variables which affect the extraction are described..
Date: June 29, 1953
Creator: Van Tuyl, H. H.
System: The UNT Digital Library
Thermal Analysis of SM-1 Core III (open access)

Thermal Analysis of SM-1 Core III

Abstract This technical report covers the thermal analysis performed on the SM-1 Core III for both steady state and transient conditions is reported. SM-1 Core III will be used as a test for Type 3 elements in a PM-2A Core. The steady state analysis indicated minimum departure from nucleate boiling ratios (DNBR) for both design and scram conditions above the minimum criteria of 1.5. Local nucleate boiling was noted in the hot internal channels and lattice passage at scram power conditions. Loss of flow transient results indicate DNBR's above 1.5, insuring that the core is safe from burnout. Bulk boiling was noted in the hot channels and lattice passage at scram power condition.
Date: June 29, 1962
Creator: Davidson, S. L.
System: The UNT Digital Library