39 Matching Results

Search Results

Results: 1 - 24 next
open access

Advanced Pressurized Water Reactor Study [Part 1]: Phase 1 Report

Description: From preface: This report covers Phase I of the authorized work, consisting of determination of the specific reactor concept and size for the most economic reactor, preparation of a reference design of the most promising concept and estimated capital and generating costs, evaluation of the variations in cost as a function of unit size, and evaluation of the reductions in ultimate costs for a power station having multiple units of the same type.
Date: July 1959
Creator: U.S. Atomic Energy Commission. Division of Reactor Development.
Partner: UNT Libraries Government Documents Department
open access

Advanced Pressurized Water Reactor Study [Part 3]: 235 Mw Coal-fired Generating Plant

Description: "This study is one of four initiated in 1958 by the Division of Reactor Development, U.S. Atomic Energy Commission, to assess the feasibility of power generation through the use of certain types of nuclear reactors. These studies are available from the Office of Technical Services, U.S. Department of Commerce, Washington 25, D.C."
Date: July 1959
Creator: U.S. Atomic Energy Commission. Division of Reactor Development.
Partner: UNT Libraries Government Documents Department
open access

Argonne High-Flux Research Reactor: AHFR Conceptual Design Study

Description: Report issued by the Argonne National Laboratory discussing high-flux research reactor design studies. As stated in the summary, "this report presents a reactor design to meet the needs of the basic research program at Argonne National Laboratory. The program requires some irradiation in thermal flux...and some beam experiments..." (p. 5). This report includes tables, and illustrations.
Date: June 1959
Creator: Link, L. E.; Armstrong, R. H.; Cameron, T. C.; Heineman, J. B.; Kelber, C. N.; Kier, P. H. et al.
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
open access

An Automatic Analyzing Monitor for Reactor Effluent Cooling Water

Description: From objective: "The objective of this work was to design, develop, assemble, and test and automatic analyzing monitor for recording the prominent isotopes in reactor effluent cooling water."
Date: May 1, 1959
Creator: Rieck, H. G.; Ratcliffe, C. A. & Schwendiman, L. C.
Partner: UNT Libraries Government Documents Department
open access

Boiling Water Reactor Study [Part 1]: 306 Mw Power Reactor Conceptual Design

Description: From introduction: In general, the objective of this study is to provide for the development of the conceptual design criteria for the most promising type of boiling water reactor and associated complete electrical generating plant consistent with a schedule calling for start of construction in July 1960.
Date: July 1959
Creator: Ebasco Services Incorporated
Partner: UNT Libraries Government Documents Department
open access

Boiling Water Reactor Study [Part 2]: Separate Studies

Description: From introduction: This section presents the principal results of the optimization study done to establish the economic basis for selection of the core and fuel design.
Date: July 1959
Creator: Ebasco Services Incorporated
Partner: UNT Libraries Government Documents Department
open access

Boiling Water Reactor Study [Part 3]: 306 Mw Coal-Fired Installation

Description: From introduction: The objectives of this study are to determine the estimated capital and energy costs of this typical conventional coal-fired installation, consistent with a schedule calling for completion of construction April 1964.
Date: July 1959
Creator: Ebasco Services Incorporated
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

Experimental Organic Cooled Reactor : Conceptual Design

Description: Report presenting the design, research programs, and design objectives for an Organic-Cooled Reactor.
Date: December 1, 1959
Creator: Huffman, John R.; Nyer, W. E. & Rainwater, J. H.
Partner: UNT Libraries Government Documents Department
open access

Fabrication of the PRTR Zircaloy-2 High Pressure Process Tubes

Description: Development of a fabrication process and the manufacture of 95 PRTR process tubes demonstrates that the commercial fabrication of high quality Zircaloy-2 pressure tubing is feasible.
Date: July 31, 1959
Creator: Knecht, R. L.
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

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

The HGCR-1, a Design Study of a Nuclear Power Station Employing a High-Temperature Gas-Cooled Reactor with Graphite-UO₂ 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

In-Pile Loop Tests of GCRE Elements (I-IT and I-I'T)

Description: Report documenting two in-pile loop experiments conducted at the Battelle Research Reactor-Gas Cooled Reactor (BRR-GCR). These experiments test heat transfer calculations and the behavior of the fuel element under severe thermal-cycling conditions.
Date: July 2, 1959
Creator: Nakazato, S.; Williams, P. M. & Wilson, W. D.
Partner: UNT Libraries Government Documents Department
Back to Top of Screen