Search Results

open access

10 MWe Sodium Deuterium Reactor Design Report

Description: From foreword: This report describes the goal of the overall SDR program to demonstrate the commercial generation of electrical power using a sodium-cooled reactor.
Date: 1959
Creator: Davis, Peter J.
Partner: UNT Libraries Government Documents Department
open access

Development of a Fuel Handling System for an Organic Moderated Reactor

Description: Abstract: This report describes the features of several systems which were rejected as inadequate, and the evaluation of a design leading to the construction of a prototype cask and its associated equipment.
Date: 1959
Creator: Leppard, J. A.
Partner: UNT Libraries Government Documents Department
open access

Generalized Heat Conduction Code for the IBM-704 Computer

Description: Report regarding a code that solves "steady-state and/or transient heat conduction problems in three-dimensional geometry" (p. 1).
Date: 1959
Creator: Fowler, T. B. & Volk, E. R.
Partner: UNT Libraries Government Documents Department
open access

The HGCR-1, a Design Study of a Nuclear Power Station Employing a High-Temperature Gas-Cooled Reactor with Graphite-UOâ‚‚ Fuel Elements

Description: "The preliminary design of a 3095-Mw(thermal), helium-cooled, graphite- moderated reactor employing sign conditions, 1500 deg F reactor outlet gas would be circulated to eight steam generators to produce 1050 deg F, 1450-psi steam which would be converted to electrical power in eight 157-Mw(electrical) turbine- generators. The over-all efficiency of this nuclear power station is 36.5%. The significant activities released from the unclad graphite-UO₂ fuel appear to be less than 0.2% of those pro… more
Date: 1959
Creator: Cottrell, William B.; Copenhaver, C. M.; Culver, H. N.; Fontana, M. H.; Kelleghan, V. J. & Samuels, G.
Partner: UNT Libraries Government Documents Department
open access

Radioactive Waste Management at Oak Ridge National Laboratory

Description: Report documenting "[t]he collection, treatment, disposal, and monitoring of radioactive wastes (solid, liquid, and gaseous) at Oak Ridge National Laboratory" (p. 2).
Date: 1959
Creator: Browder, F. N.
Partner: UNT Libraries Government Documents Department
open access

Specifications and Fabrication Procedures for APPR-1 Core II Stationary Fuel Elements

Description: Report regarding the design requirements and manufacturing procedures for the stationary fuel component proposed for operation in the second core loading of the Army Package Power Reactor at Fort Belvoir, Virginia.
Date: 1959
Creator: Cunningham, J. E.; Beaver, R. J.; Robertson, R. D. & Edgar, E. C.
Partner: UNT Libraries Government Documents Department
open access

Thermonuclear Project Semiannual Report, January 31, 1959

Description: Report describing progress made on the Oak Ridge National Laboratory Thermonuclear Program called the "Sherwood Project."
Date: 1959
Creator: Oak Ridge National Laboratory
Partner: UNT Libraries Government Documents Department
open access

Design Bases for ICPP Waste Calcination Facility

Description: Report regarding a waste calcination unit that "will convert the fission product-containing aluminum nitrate solutions" "to granular alumina and fission product oxides" (p. 5).
Date: January 16, 1959
Creator: MacQueen, D. K. & Stevens, J. I.
Partner: UNT Libraries Government Documents Department
open access

Heat Transfer in an Annulus with Asymmetric Heating

Description: Report concerning the "determination of the validity of using tube flow correlations for calculating pressure drop and heat transfer characteristics in thin annuli," the "validity of using Stein's heat flux asymmetry correction for parallel planes to calculate the heat transfer in asymmetrically heated thin annuli," and the "investigation of the effects of eccentricity on pressure drop, heat transfer, and temperature distribution in concentric ring fuel elements" (p. 5).
Date: February 1959
Creator: Lisin, Alexander Vladimir; Mackewicz, W. V. & Reynolds, William C., 1933-2004
Partner: UNT Libraries Government Documents Department
open access

Particle Accelerator Division Summary Report: April 15, 1958 through October, 1958

Description: Report issued by the Argonne National Laboratory discussing a summary report of work completed between April and October, 1958. Summaries of the studies conducted and work completed are presented. This report includes tables, and illustrations.
Date: February 1959
Creator: Argonne National Laboratory. Particle Accelerator Division.
Partner: UNT Libraries Government Documents Department
open access

Lecture Notes on Reactor Shielding

Description: Report issued by the Argonne National Laboratory discussing the shielding of radiation produced by nuclear reactors. As stated in the introduction, "these lectures will be an attempt to discuss the design of a reactor shield and the solution of the associated shielding problems by simple hand-computing methods" (p. 19). This report includes tables, and illustrations.
Date: March 1959
Creator: Grotenhuis, Marshall
Partner: UNT Libraries Government Documents Department
open access

Preliminary Design 30,000 KW Prototype Partially Enriched Uranium, Gas Cooled, Graphite Moderated Nuclear Power Plant (Prototype of an Optimum Plant) for United States Atomic Energy Commission, Idaho Operations Office contract no. AT(10-1)-925

Description: Report containing the preliminary design for a nuclear reactor plant and its facilities. Includes a description of systems, safety procedures, costs, and a glossary.
Date: March 1959
Creator: Kaiser Engineers
Partner: UNT Libraries Government Documents Department
open access

Savannah River Project Site Report: 30,000 KW Prototype Partically Enriched Uranium Gas Cooled, Graphite Moderated Nuclear Power Plant for United States Atomic Energy Commission Idaho Operations Office

Description: Report describing a modified prototype of a nuclear reactor that uses partially uranium-enriched fuel and is cooled by helium. The construction site, site safety aspects, and design and construction costs are included.
Date: March 1959
Creator: ACF Industries Incorporated. Nuclear Products - ERCO Division.
Partner: UNT Libraries Government Documents Department
open access

Ionium Recovery Plant Design Report: Topical Report

Description: This report documents the study of the recovery of thorium by solvent extraction in pilot plant pulse columns, using a filtered liquor from nitric acid digestions of the raffinate cake produced by the ethyl ether extraction of uranium from pitchblende.
Date: April 15, 1959
Creator: Edwards, R. M.; Fariss, R. H. & Werkema, R. G.
Partner: UNT Libraries Government Documents Department
open access

Army Gas-Cooled Reactor Systems Program Monthly Progress Report: April 1959

Description: Abstract: This monthly progress report covers the activities of the Army Gas-Cooled Reactor System Program for April 1959. The program includes a water-moderated heterogeneous reactor (Gas-Cooled Reactor Experiment I), a graphite-moderated homogeneous reactor (Gas-Cooled Reactor Experiment II), a mobile gas-cooled reactor (ML-1), and the coordination of the Gas Turbine Test Facility. [It reports] the progress of each project, the associated tests and data evaluation, the applicable design crit… more
Date: May 25, 1959
Creator: Aerojet-General Corporation
Partner: UNT Libraries Government Documents Department
Back to Top of Screen