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300,000-KWE SGR Nuclear Power Plant of Current Technology
Abstract: This report describes a 300,000-kwe, sodium-cooled, graphite-moderated nuclear power plant based on existing technical information.
Date:
August 1, 1960
Creator:
Renard, J.; Peckinpaugh, C. L. & Aronstein, R. E.
System:
The UNT Digital Library
ABWR: PL-2 Design Report
From preface: This report satisfies the quarterly progress report requirements for PL-1 and PL-2 plant design work for the period ending September 30, 1960 At present time a SL-1 Core 2 is under construction. This is a replacement core for SL-1 (ALPR) and will be identical to a PL-2 core; a PL condenser is under test at the SL-1 facility; final construction plans for PL components and modules which are not site sensitive will be completed in March 1961.
Date:
October 15, 1960
Creator:
Combustion Engineering, inc. Nuclear Division.
System:
The UNT Digital Library
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
Aircraft Reactor Test Removal and Disassembly
Report documenting the dissection of a reactor called the Aircraft Reactor Test (ART). Includes the removal of the reactor from its test cell, component removal, and plans for a for a disassembly building facility.
Date:
1960?
Creator:
Abbatiello, A. A. & McQuilkin, F. R.
System:
The UNT Digital Library
Argonne National Laboratory Idaho Division Summary Report: July-September, 1960
Report issued by the Argonne National Laboratory covering a summary report of the work conducted by the Idaho Division. Experimental work and progress made on reactors are presented. This report includes tables, illustrations, and photographs.
Date:
1960
Creator:
Argonne National Laboratory. Idaho Division.
System:
The UNT Digital Library
Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: July 1 - December 31, 1959
Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.
Date:
February 15, 1960
Creator:
Aerojet-General Corporation
System:
The UNT Digital Library
Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1960
Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.
Date:
July 31, 1960
Creator:
Aerojet-General Corporation
System:
The UNT Digital Library
Assembly of Fifty Prototype Fuel Elements for the Experimental Gas-Cooled Reactor
Report that describes the Oak Ridge National Laboratory Experimental Gas-Cooled Reactor, problems with the procurement and assembly of its components, and its economic feasibility.
Date:
December 23, 1960
Creator:
Wick, E. A. & Heestand, R. L.
System:
The UNT Digital Library
Automatic Control of T7 Tanker Boiling Water Reactor Propulsion System: Preliminary Design and Economic Evaluation
From introduction: "This report sets forth the results of a technical and economic analysis of automatic propulsion system control as a possible design improvement in the direct cycle boiling water reactor propulsion system in a T7 tanker."
Date:
September 1, 1960
Creator:
U.S. Atomic Energy Commission
System:
The UNT Digital Library
Boiling Songs and Associated Mechanical Vibrations
From introduction: The study is based entirely on observations which have been made at a number of different installations at which boiling songs and vibrations were noted during heat transfer experiments.
Date:
June 30, 1960
Creator:
Firstenberg, H.
System:
The UNT Digital Library
Calculated Equilibrium Distributions for the Uranyl Nitrate - Tributyl Phosphate - Dilute Nitric Acid System for Temperatures Between 25 and 75 C
Report discussing the "equilibrium uranium distribution between an aqueous nitric acid solution and a 30 per cent by volume solution of tributyl phosphate in a hydrocarbon diluent" (p. 2). This includes the necessary equations.
Date:
August 12, 1960
Creator:
Wilburn, N. P.
System:
The UNT Digital Library
Chemical Technology Division Annual Progress Report, August 31, 1960
Report documenting the ongoing research of the Oak Ridge National Laboratory's Chemical Technology Division. This report includes tables, diagrams, graphs, and articles related to chemical technology.
Date:
1960
Creator:
Oak Ridge National Laboratory. Chemical Technology Division.
System:
The UNT Digital Library
Cost Study of a 100-Mw(e) Direct-Cycle Boiling Water Reactor Plant
Report issued by the Argonne national Laboratory discussing a technical and economic evaluation of a direct-cycle light-water boiling reactor designed for natural circulation and internal steam-water separation. The reference 100-Mw(e) reactor power plant design evolved from the study should have the best chance (compared to similar plants) of approaching the 8 to 9 mill/kwh total power-cost level. This report includes tables, and illustrations.
Date:
July 1960
Creator:
Bullinger, C. F. & Harrer, J. M.
System:
The UNT Digital Library
Description of the Thermal Hydraulics Laboratory at Hanford
Report describing the thermal hydraulics facilities at Hanford Laboratories as well as its operation, equipment, and systems.
Date:
June 2, 1960
Creator:
Batch, J. M. & Toyoda, K. G.
System:
The UNT Digital Library
Design Evaluation and Comparison 200 MWe Boiling Dâ‚‚O Pressure Tube Indirect and Direct Cycle Power Reactor Plants
From foreword: This report is concerned with the investigation of an indirect cycle plant which was the subject of a joint study between Sargent & Lundy and NDA.
Date:
June 30, 1960
Creator:
unknown
System:
The UNT Digital Library
Design Study: Sodium Modular Reactor
This study was undertaken for the USAEC under Contract AT(04-3)-189, Project Agreement No. 6, to investigate desirable features of a sodium cooled, graphite moderated uranium fueled power reactor using the modular concept, and, based on this investigation, evaluate the economic potential of this reactor type.
Date:
January 15, 1960
Creator:
General Electric Company
System:
The UNT Digital Library
A Device for Continuous Detection of Hydrogen in Sodium
Abstract: A device to detect the presence of hydrogen in sodium has been developed. Such a device, installed in a sodium heated steam generator, would signal the presence of water in the sodium resulting from a leak in the sodium-water barrier.
Date:
December 15, 1960
Creator:
Strahl, H.
System:
The UNT Digital Library
Dissolution of Power Reactor Fuel Cores
Report discussing the dissolution of simulated fuel cores. Equipment and procedures are discussed along with significant characteristics of the core materials.
Date:
August 26, 1960
Creator:
Blaine, H. T.
System:
The UNT Digital Library
Engineering Evaluation of a Mixed Alloy Fuel Element Irradiated at Elevated Temperatures in the SRE
Abstract: A fuel material evaluation was made by destructively examining a full-scale experimental fuel element, irradiated in the SRE to a maximum of 850 Mwd/MTU.
Date:
June 1, 1960
Creator:
Ballif, J. L.; Hayward, B. R. & Walter, J. W.
System:
The UNT Digital Library
ETR Nuclear Instrumentation : Final Report
Report regarding the primary nuclear instrumentation at the Engineering Test Reactor (ETR) and early difficulties.
Date:
February 3, 1960
Creator:
Hanson, D. C.
System:
The UNT Digital Library
An Evaluation of Fossil Superheat for Nuclear Power Plants
From introduction: This report sets forth the results of a study of the evaluation of fossil fuel superheat in nuclear power plants.
Date:
October 1960
Creator:
unknown
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
Evaluation of the Technical, Economic and Practical Feasibility of Radiation Preservation of Fish
From abstract: Based on exploratory studies conducted over the last six years on the radiation-preservation of various marine species, it is apparent that low dose substerilization-radiation treatment of certain selected sea foods can provide advantages for the procurer, processor, distributor and consumer of edible marine products.
Date:
1960?
Creator:
Proctor, Bernard E.; Goldblith, Samuel A.; Nickerson, John T. R. & Farkas, D. F.
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