Comparison of Radiation-Induced Graft Copolymerization Untilizing Electron Accelerators and Isotope Sources as Radiation Initiators (open access)

Comparison of Radiation-Induced Graft Copolymerization Untilizing Electron Accelerators and Isotope Sources as Radiation Initiators

"Graft polymers were made by Co60 mutual irradiation of mixtures of styrene and methyl acrylate in contact Teflon. These graft copolymers were analyzed by infra-red absorption and their composition determined. The composition of the graft copolymer formed from styrene and methyl acrylate was different from that which is predicted by the copolymer composition equation."
Date: May 8, 1961
Creator: unknown
System: The UNT Digital Library
The Influence of Isotopic Composition on the Maximum in the Cosmic Ray Energy Spectra (open access)

The Influence of Isotopic Composition on the Maximum in the Cosmic Ray Energy Spectra

"The previously found maximum in the cosmic radiation energy spectrum is discussed, and the possibility that it arises in part from a misinterpretation of the data due to oversimplifying assumptions about the composition of the beam is examined. The importance that lack of recognition of isotopic composition may have is pointed out, and it is clear that this importance is strongly dependent on the measurements made and on the cut-off rigidity."
Date: May 8, 1961
Creator: Appa Rao, M.V.K. &
System: The UNT Digital Library
The Design, Installation, and Testing of the Gas-Cooled Reactor UO₂ Irradiation Experiment at the NRTS (open access)

The Design, Installation, and Testing of the Gas-Cooled Reactor UO₂ Irradiation Experiment at the NRTS

Report regarding sixteen experiments performed with a miniature re-entrant gas loop. Includes design problems and difficulties encountered, as well as their solutions.
Date: September 8, 1961
Creator: Porter, E. H.
System: The UNT Digital Library
Hazards Evaluation of the SM-1 Penetrated Gasket (open access)

Hazards Evaluation of the SM-1 Penetrated Gasket

Abstract: This technical report describes the as-constructed SM-1 penetrated gasket designed for SM-1 Core and Flow Instrumentation (Task XIV). This report supplements APAE No. 79, The Summary Hazards Report for Task XIV, and evaluates the effects of a postulated failure of this gasket. The effects of failure on the Maximum Credible Accident are determined and conclusions and recommendations for the use of this gasket are made.
Date: September 8, 1961
Creator: Coombe, J. R.; Gebhardt, F. G. & James, B.
System: The UNT Digital Library
Steady State and Transient Thermal and Hydraulic Analysis of SM-2 Termination Report (open access)

Steady State and Transient Thermal and Hydraulic Analysis of SM-2 Termination Report

Abstract: Thermal characteristics of the SM-2 core were analyzed at steady state and loss of flow conditions. For steady state operation, the steady state code STDY-3 was used. For transients during a loss of flow accident, ART-02, a one-dimensional code, was used. This analysis indicates the SM-2 core is safe from burnout under steady state operation at design power level (28 tMW) because (1) no nucleate boiling exists, and (2) the minimum burnout ratio is above 2.0. The core is safe from burnout under loss of flow transient because the minimum burnout ratio in the hottest element channel of 1. 82 is above the minimum design criteria of 1. 5.
Date: September 8, 1961
Creator: Segalman, I. & Bradley, P. L.
System: The UNT Digital Library
Pure Metals from Chemical Processes (open access)

Pure Metals from Chemical Processes

From introduction: "Discussions of some unit chemical processes that are especially effective in obtaining metals of high purity are presented here."
Date: January 8, 1962
Creator: Wilhelm, H. A. & Peterson, David T.
System: The UNT Digital Library
Gamma Ray Efficiencies for Well Type Scintillation Crystals (open access)

Gamma Ray Efficiencies for Well Type Scintillation Crystals

From Abstract : "Gamma ray efficiencies for various sized well type NaI(Ti) crystals have been calculated using an IBM 704 digital computer. The adjustable parameters in the program are the gamma ray energy, the heights and diameters of the crystal and the well, the thickness of the well lining, and the positions of the (point) source inside the well. Some typical results are presented in graphical form."
Date: February 8, 1963
Creator: Dingus, Ronald S. & Stewart, M. G.
System: The UNT Digital Library
Program for the Development of Plutonium Recycle for Use in Light Water Moderated Reactors Quarterly Progress Report: January 1 - March 31, 1963. (open access)

Program for the Development of Plutonium Recycle for Use in Light Water Moderated Reactors Quarterly Progress Report: January 1 - March 31, 1963.

A research program is being conducted to obtain experimental data in the irradiation of plutonium-enriched fuel to confirm a theoretical model for predicting isotopic composition and reactivity changes in plutonium-enriched, light-water-moderated reactors. All program efforts have been temporarily deferred except for those associated with the irradiation of the program fuel element in the VBWR. The program fuel element was exposed to a burnup of 465 MWD/T during the quarter which brings the total to 2334 MWD/T. On the basis of the computed isotopic composition, the burnup obtained was 1450 MWD/T.
Date: April 8, 1963
Creator: Robkin, M. A.
System: The UNT Digital Library
A Summary of the Geology of Crooks Gap, Fremont County, Wyoming, as Related to Uranium Resources (open access)

A Summary of the Geology of Crooks Gap, Fremont County, Wyoming, as Related to Uranium Resources

A report summarizing the geology of Crooks Gap, Fremont County, Wyoming, as related to Uranium Resources
Date: March 8, 1967
Creator: Curry, Donald L.
System: The UNT Digital Library