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300,000-KWE SGR Nuclear Power Plant of Current Technology

Description: 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.
Partner: UNT Libraries Government Documents Department
open access

ABWR: PL-2 Design Report

Description: 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.
Partner: UNT Libraries Government Documents Department
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An Advanced Sodium-Graphite Reactor Nuclear Power Plant

Description: 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.
Partner: UNT Libraries Government Documents Department
open access

Aircraft Reactor Test Removal and Disassembly

Description: 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.
Partner: UNT Libraries Government Documents Department
open access

Argonne National Laboratory Idaho Division Summary Report: July-September, 1960

Description: 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.
Partner: UNT Libraries Government Documents Department
open access

Calculated Equilibrium Distributions for the Uranyl Nitrate - Tributyl Phosphate - Dilute Nitric Acid System for Temperatures Between 25 and 75 C

Description: 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.
Partner: UNT Libraries Government Documents Department
open access

Chemical Technology Division Annual Progress Report, August 31, 1960

Description: 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.
Partner: UNT Libraries Government Documents Department
open access

Cost Study of a 100-Mw(e) Direct-Cycle Boiling Water Reactor Plant

Description: 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.
Partner: UNT Libraries Government Documents Department
open access

Description of the Thermal Hydraulics Laboratory at Hanford

Description: 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.
Partner: UNT Libraries Government Documents Department
open access

Design Study: Sodium Modular Reactor

Description: 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
Partner: UNT Libraries Government Documents Department
open access

A Device for Continuous Detection of Hydrogen in Sodium

Description: 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.
Partner: UNT Libraries Government Documents Department
open access

Dissolution of Power Reactor Fuel Cores

Description: 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.
Partner: UNT Libraries Government Documents Department
open access

ETR Nuclear Instrumentation : Final Report

Description: Report regarding the primary nuclear instrumentation at the Engineering Test Reactor (ETR) and early difficulties.
Date: February 3, 1960
Creator: Hanson, D. C.
Partner: UNT Libraries Government Documents Department
open access

Evaluation of Irradiated OMRE Fuel Elements First Core Loading

Description: 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.
Partner: UNT Libraries Government Documents Department
open access

Evaluation of the Technical, Economic and Practical Feasibility of Radiation Preservation of Fish

Description: 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.
Partner: UNT Libraries Government Documents Department
open access

An Experimental Gamma Irradiator for Hospital Sterilization

Description: 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.
Partner: UNT Libraries Government Documents Department
open access

Fuel Core Tester - UT-2

Description: Report that "describes an instrument that nondestructively tests uranium fuel element cores by ultrasonic methods" (p. 2).
Date: July 18, 1960
Creator: Frederick, C. L. & Waldkoetter, G. L.
Partner: UNT Libraries Government Documents Department
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