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Feasibility Study, Optimum Natural Uranium, Gas Cooled, Graphite Moderated Nuclear Power Plant for United States Atomic Energy Commission, Idaho Operations Office (open access)

Feasibility Study, Optimum Natural Uranium, Gas Cooled, Graphite Moderated Nuclear Power Plant for United States Atomic Energy Commission, Idaho Operations Office

Report containing "a discussion of the feasibility design and cost estimates for a gas cooled, natural uranium, graphite moderated power plant optimized for minimum power cost" (p. 3).
Date: April 1, 1958
Creator: ACF Industries Incorporated. Nuclear Products - ERCO Division.
Object Type: Report
System: The UNT Digital Library
Feasibility Study, Optimum Partially Enriched Uranium, Gas Cooled, Graphite Moderated for United States Atomic Energy Commission, Idaho Operations Office (open access)

Feasibility Study, Optimum Partially Enriched Uranium, Gas Cooled, Graphite Moderated for United States Atomic Energy Commission, Idaho Operations Office

Report that contains "a preliminary design and feasibility studies of gas cooled, graphite moderated, nuclear power plants" (p. 1).
Date: April 1, 1958
Creator: ACF Industries Incorporated. Nuclear Products - ERCO Division.
Object Type: Report
System: The UNT Digital Library
Army Package Power Reactor APPR-1 Operating Manual and Inspection and Service Manual (open access)

Army Package Power Reactor APPR-1 Operating Manual and Inspection and Service Manual

Report containing basic operating instructions for the operation of the Army Package Power Reactor. This includes descriptions of the the plant's systems, operations, and safety procedures.
Date: February 1958
Creator: Alco Products (Firm)
Object Type: Report
System: The UNT Digital Library
Distribution of Uranyl Nitrate Between Al(NO3)3 and Tributyl Phosphate (open access)

Distribution of Uranyl Nitrate Between Al(NO3)3 and Tributyl Phosphate

From abstract: "The distribution of uranyl nitrate was measured from aluminum nitrate and nitric acid solutions into diluted tri-n-butyl phosphate. This information is useful for designing solvent extraction processes for recovery of uranium from aluminum nitrate or nitric acid solutions."
Date: March 1958
Creator: Ames, Donald P. & Karraker, David G.
Object Type: Report
System: The UNT Digital Library
Li⁶ and Li⁷ (n. 2n) Cross Sections at 14.1 Mev (open access)

Li⁶ and Li⁷ (n. 2n) Cross Sections at 14.1 Mev

Abstract: "An absolute measurement of the 14.1-Mev (n, 2n) cross sections of Li-6 and Li-7 has been made using the large scintillator technique, resulting in cross sections in barns of 0.070 +/- 0.006 and 0.056 +/- 0.005 for Li-6 and Li-7, respectively."
Date: May 29, 1958
Creator: Ashby, V. J.; Catron, H. C.; Newkirk, Lester L.; Taylor, C. J. & Williamson, M. A.
Object Type: Report
System: The UNT Digital Library
Core Design and Characteristics for the Consolidated Edison Reactor (open access)

Core Design and Characteristics for the Consolidated Edison Reactor

The general purpose of this report is to present the major characteristics and design of the Consolidated Edison Thorium Reactor (CETR) core
Date: August 18, 1958
Creator: Babcock & Wilcox Company
Object Type: Report
System: The UNT Digital Library
Liquid Metal Fuel Reactor Experiment, Quarterly Technical Report: April 1958 - June 1958 (open access)

Liquid Metal Fuel Reactor Experiment, Quarterly Technical Report: April 1958 - June 1958

Quarterly technical report discussing progress and activities of the Liquid Metal Fuel Reactor Experiment.
Date: April 1958
Creator: Babcock & Wilcox Company
Object Type: Report
System: The UNT Digital Library
Liquid Metal Fuel Reactor Experiment Quarterly Technical Report: July - September 1958 (open access)

Liquid Metal Fuel Reactor Experiment Quarterly Technical Report: July - September 1958

Report containing research and development undertaken regarding the Liquid Metal Fuel Reactor Experiment.
Date: October 1958
Creator: Babcock & Wilcox Company
Object Type: Report
System: The UNT Digital Library
Nuclear Merchant Ship Reactor:  Determination of the Purification Rate for Normal Operation (open access)

Nuclear Merchant Ship Reactor: Determination of the Purification Rate for Normal Operation

The objective of this study is to establish a primary loop purification rate for normal operation to (1) maintain the activity created in the primary coolant water by corrosion products and other impurities (excluding fission products) at tolerable level and (2) minimize the crud deposition on the core heat-transfer surfaces.
Date: June 1958
Creator: Babcock & Wilcox Company
Object Type: Report
System: The UNT Digital Library
Uranium Exploration on Palangana Salt Dome, Duval County Texas (open access)

Uranium Exploration on Palangana Salt Dome, Duval County Texas

Reporting investigations into the lithologic and structural ore controls as revealed by this exploration program.
Date: December 1958
Creator: Barnes, John C.
Object Type: Report
System: The UNT Digital Library
Engineering Study on Underground Construction of Nuclear Power Reactors (open access)

Engineering Study on Underground Construction of Nuclear Power Reactors

Engineering study on underground construction of nuclear power reactors.
Date: April 15, 1958
Creator: Beck, Christian
Object Type: Report
System: The UNT Digital Library
Applied Nuclear Physics Division Annual Progress Report for Period Ending September 10, 1956 (open access)

Applied Nuclear Physics Division Annual Progress Report for Period Ending September 10, 1956

Report issued by the Oak Ridge National Laboratory discussing work completed by the Applied Nuclear Physics Division during 1956. Summaries of experiments conducted and project developments are presented. This report includes tables, illustrations, and photographs.
Date: November 20, 1958
Creator: Blizard, E. P.; Simon, A.; Callihan, A. D.; Clifford, C. E.; Maienschein, F. C. & Peelle, R. W.
Object Type: Report
System: The UNT Digital Library
A Survey of Non-Fuel-Bearing Materials for the Marine Gas-Cooled Reactor (open access)

A Survey of Non-Fuel-Bearing Materials for the Marine Gas-Cooled Reactor

Results of an initial examination of non-fuel-bearing materials for the Marine Gas Cooled Reactor are presented. Areas given specific attention include structural and cladding materials and graphite moderator. Other areas not included because of classification include zirconium hydride moderator and control materials. In each report section, available pertinent information is summarized and a plan for future work is given.
Date: May 1, 1958
Creator: Bokros, J. C.; Dijkstra, L; & Merten, U.
Object Type: Report
System: The UNT Digital Library
Evaluation of Foreign Multiplier Phototubes (open access)

Evaluation of Foreign Multiplier Phototubes

"Several multiplier phototubes produced by England, Russia, or Switzerland were evaluated for amplification, photocathode sensitivity, photo-electron collection efficiency, cathode uniformity, and dark current. A description of the various tubes by designation numbers is given, along nth a description of techniques and equipment used in testing."
Date: January 1, 1958
Creator: Bolakas, J. & Parker, P G.
Object Type: Report
System: The UNT Digital Library
Reconnaissance for Uranium in the Elqui-Vicuña area, Province of Coquimbo, Chile (open access)

Reconnaissance for Uranium in the Elqui-Vicuña area, Province of Coquimbo, Chile

Abstract: The Elqui-Vicuna area, Coquimbo province, Chile, was selected for uranium reconnaissance on the basis of two known uranium occurrences and favorable area-wide geologic indications of the possible presence of uranium in commercial quantities.
Date: September 1958
Creator: Bowes, William A.; Knowles, Paul H.; C., Mario Serrano & H., Erik Klohn
Object Type: Report
System: The UNT Digital Library
Reconnaissance for Uranium in the Iquique Area, Province of Tarapaca, Chile (open access)

Reconnaissance for Uranium in the Iquique Area, Province of Tarapaca, Chile

Introduction: This exploratory work was undertaken as a preliminary evaluation of the area's uranium potential, and was limited to reconnaissance for favorable geologic indications of uranium, which included visits to selected localities and mining districts.
Date: October 1958
Creator: Bowes, William A.; Knowles, Paul H.; C., Mario Serrano & H., Erik Klohn
Object Type: Report
System: The UNT Digital Library
Trans-Plutonium Isotope Buildup by Neutron Irradiation of Plutonium (open access)

Trans-Plutonium Isotope Buildup by Neutron Irradiation of Plutonium

Graphs for estimation of plutonium and trans-plutonium isotopic content of irradiated plutonium reactor fuel of various initial isotopic compositions.
Date: December 15, 1958
Creator: Brauer, F. P. & Burley, Helen H.
Object Type: Report
System: The UNT Digital Library

Plate I Geologic Map of the Crooks Map District, Freemont District, Wyoming

Geologic map of the Crooks Map District, Freemont District, Wyoming showing core drill holes prepared for a report by U.S. Atomic Energy Commission, Grand Junction Office.
Date: October 24, 1958
Creator: Bromley, Charles P.
Object Type: Map
System: The UNT Digital Library
Stratigraphic Drilling in the Crooks Gap Area (open access)

Stratigraphic Drilling in the Crooks Gap Area

Discussing a drilling program planned to investigate the lithology and internal stratigraphy of the Wasatch formation and to determine the depth to the underlying surface of unconformity of the basal contact of the Wasatch formation.
Date: October 24, 1958
Creator: Bromley, Charles P.
Object Type: Report
System: The UNT Digital Library
Plant Transient Analysis of the APPR-1 by Analog Computer Methods ; Task No. IV (open access)

Plant Transient Analysis of the APPR-1 by Analog Computer Methods ; Task No. IV

Phase I - Plant Transient Analysis. Behavior of the basic and refined kinetic models differs only slightly. It is therefore suggested that the basic model be used in any studies where the improvement in fidelity attainable fro the refined model is not warranted by the complexities introduced by the addition of function generator to the analog circuitry and derivation of the function to be programmed. The parameter responses of both kinetic models appear to be essentially similar to those of the plant with the exception of the primary pressure. In the pressurizer analysis it was noted that the primary system pressure surges of the model should be higher than those of the plant because of the adiabatic steam compression assumed in the model derivation. the fact that the mode surge is very much greater indicates that the compression process is far from adiabatic. A more detailed and complex model of the pressurizer, one that evaluates heat transfer in the steam pocket boundaries, would therefore reduce the costly conservatism otherwise necessary in the specification of pressurizer vessel size. Phase II - Xenon Reactivity Transients. On the basis of this study an analog computer circuit has been presented which accurately represents bank …
Date: October 1, 1958
Creator: Brondel, J. O. & Tomonto, J. R.
Object Type: Report
System: The UNT Digital Library
Analysis of Extended Zero Power Experiments on the Army Package Power Reactor : ZPE-2 (open access)

Analysis of Extended Zero Power Experiments on the Army Package Power Reactor : ZPE-2

Introduction: This report is principally concerned with analysis of measurements taken on the APPR-1 core during the course of the extended Zero Power Experiments (ZPE-2). The bulk of these measurements are reported in APAE No. 21. There are some additional measurements reported in APAE Memo 115. In addition to the analysis of the ZPE-2 data some re-evaluation has been made of a few of the results obtained from the first set of Zero Power Experiments (ZPE-1). The ZPE-1 measurements are reported in APAE No. 8. During the course of analysis work it became apparent that a considerable amount of basic experimental data had been taken on the APPR-1 core. It seemed worthwhile to organize this report in such a fashion that other investigators could make maximum use of this data. It provides excellent opportunity for individuals and groups interested in basic reactor reactor analysis problems to check calculational techniques. An attempt has been made to include all of the fundamental information concerning the material content and geometry of the APPR-1. This material is in included in the Appendices. In addition, cross-section files and group constants have been listed rather extensively in order that other investigators could compare results presented in …
Date: May 7, 1958
Creator: Byrne, B. J. & Oby, P. V.
Object Type: Report
System: The UNT Digital Library
Radiation Bursts in U235 Solutions (open access)

Radiation Bursts in U235 Solutions

From abstract: "Calculations are made of the magnitude of the radiation bursts that can occur in a mixer-settler and in a large tank containing U235 solution if the concentration gets out of control. Various rates of increase in concentration are studied and various restraints are imposed on the expansion of the systems. The neutron kinetics equations, with five groups of delayed neutrons, and the equations relating the neutron flux to the pressure and volume of the gas formed by fission fragments are combined into a single first-order nonlinear differential matrix equation which is solved numerically on the IBM 650. In a mixer-settler containing 9.7 kg of U235 the magnitude of the burst was calculated to be about 10^17 fissions, both for low rates of increase in reactivity (<[or equal to]0.01% per sec) regardless of the confinement, and for an unconfined system regardless of the rate of increase reactivity. In a tank containing 88.9 kg of U235 successive bursts of about 10^19 fissions were calculated to occur about 0.5 second apart when the rate of increase in reactivity was about 0.1% per second."
Date: September 1958
Creator: Clark, Hugh K.
Object Type: Report
System: The UNT Digital Library
Determination of Burnout Limits of Polyphenyl Coolants : Summary Report (open access)

Determination of Burnout Limits of Polyphenyl Coolants : Summary Report

Report documenting an investigation undertaken "to establish the burnout limits of a polyphenyl mixture (...), diphenyl, Santowax R, and monoisopropyl-biphanyl for various pressures, fluid velocities, and fluid temperatures" (p. 7).
Date: February 14, 1958
Creator: Core, T. C. & Sato, K.
Object Type: Report
System: The UNT Digital Library
Hydromagnetic Instabilities Caused by Runaway Electrons (open access)

Hydromagnetic Instabilities Caused by Runaway Electrons

"The possibility of the excitation of hydromagnetic instabilities caused by a beam of runaway electronics is investigated. It is found that if the wave length and frequency of the wave are such that the Doppler shift of the frequency due to the runaways' motion causes the electrons to see their cyclotron frequency, and if the electric field rotates in the same direction as the electrons do about the confining magnetic field, then an instability occurs."
Date: 1958
Creator: Dawson, J. M. & Bernstein, Ira B.
Object Type: Report
System: The UNT Digital Library