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An Advanced Sodium-Graphite Reactor Nuclear Power Plant
Abstract: This report describes an advanced sodium-cooled, graphite-moderated nuclear power plant which utilizes high-pressure, high-temperature steam to generate electricity at a high thermal efficiency.
Date:
March 15, 1960
Creator:
Churchill, J. R. & Renard, J.
System:
The UNT Digital Library
Evaluation of Irradiated OMRE Fuel Elements First Core Loading
Abstract: Irradiated fuel elements from the Organic Moderated Reactor Experiment (OMRE) first core loading have been examined and evaluated to determine: (1) the stability of the floating plate fuel element design, (2) the stability of the stainless steel clad UO2 - stainless steel cermet core fuel plates under irradiation and exposure to the organic coolant, (3) the extent and nature of deposits on the fuel element services, and (4) the distribution of burnup in the fuel elements.
Date:
March 1, 1960
Creator:
Walter, J. H.; Leirich, J. F. & Calkins, G. D.
System:
The UNT Digital Library
An Experimental Gamma Irradiator for Hospital Sterilization
From foreword: This report presents the preliminary design of a gamma irradiator intended for use as an experimental hospital sterilizer.
Date:
March 7, 1960
Creator:
Frankfort, J. Harry; Haram, S. & Wallach, S.
System:
The UNT Digital Library
Halogen Collector Test Program
Report documenting the Halogen Collector Test program, which was undertaken to provide "methods of removing trace quantities of radioactive iodine from an air stream" (p. 1). The report includes designs of the program and the test facility, test results, analysis of these results, and encountered problems. Appendices begin on page 38.
Date:
March 1, 1960
Creator:
Arthur D. Little, Inc.
System:
The UNT Digital Library
Heavy-Water-Moderated Power Reactors: a Status Report
From introduction: "Evaluation of the present economic and technological status of power reactors that are cooled and moderated by heavy water and fueled with natural uranium."
Date:
March 1960
Creator:
Babcock, Dale Friend
System:
The UNT Digital Library
Liquid Metal Fuel Reactor Experiment: Induction Welding for Remote Maintenance -- Final Report
Report concerning the technical feasibility of induction welding for use in remote maintenance at the Liquid Metal Fuel Reactor Experiment. Includes descriptions of the device used, test procedures, and results.
Date:
March 1960
Creator:
Dean, D. E.
System:
The UNT Digital Library
Proposal for an Advanced Engineering Test Reactor : ETR II
Report containing "the results of a study which was directed at providing additional experimental loop irradiation space for the AEC-DRD testing program. It was a premise that the experiments allocated to this reactor were those that could not be accommodated in the MTR, ETR or in existing commercial test reactors" (p. 5).
Date:
March 17, 1960
Creator:
deBoisblanc, D. R.
System:
The UNT Digital Library
Thermal Cycling Tests of Porous Uranium
Abstract: It has been proposed that a fuel element containing porous uranium be used for moderately high temperature applications. In an effort to determine the structural integrity of this type of fuel body, thermal cycling tests have been conducted on porous uranium.
Date:
March 15, 1960
Creator:
Wilkinson, L. E.
System:
The UNT Digital Library