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Reactor Development Program Progress Report: April 1963 (open access)

Reactor Development Program Progress Report: April 1963

Report issued by the Argonne National Laboratory discussing progress made by the Reactor Development Program during April 1963. Reactor physics, experiments, and safety studies are presented. This report includes tables, and illustrations.
Date: May 15, 1963
Creator: Adams, R. M. & Glassner, A.
Object Type: Report
System: The UNT Digital Library
Reactor Development Program Progress Report: March 1963 (open access)

Reactor Development Program Progress Report: March 1963

Report issued by the Argonne National Laboratory discussing progress made by the Reactor Development Program during March 1963. Reactor physics, experiments, and safety studies are presented. This report includes tables, and illustrations.
Date: April 15, 1963
Creator: Adams, R. M. & Glassner, A.
Object Type: Report
System: The UNT Digital Library
Technical Feasibility and Economic Potential of the Variable Moderator Reactor: Final Report (open access)

Technical Feasibility and Economic Potential of the Variable Moderator Reactor: Final Report

Foreword: This report covering the technical feasibility and economic potential of the VMR completes the requirements of Phases II and III of the program outlined in American-Standard Proposal No. P-470A.
Date: December 15, 1960
Creator: Advanced Technology Laboratories
Object Type: Report
System: The UNT Digital Library
Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: July 1 - December 31, 1959 (open access)

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
Object Type: Report
System: The UNT Digital Library
Army Gas-Cooled Reactor Systems Program Quarterly Progress Report: July 1 - September 30, 1963 (open access)

Army Gas-Cooled Reactor Systems Program Quarterly Progress Report: July 1 - September 30, 1963

Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile nuclear power plant for military field operation.
Date: November 15, 1963
Creator: Aerojet-General Corporation
Object Type: Report
System: The UNT Digital Library
Army Gas-Cooled Reactor Systems Program Quarterly Progress Report: October 1 - December 31, 1963 (open access)

Army Gas-Cooled Reactor Systems Program Quarterly Progress Report: October 1 - December 31, 1963

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, 1963
Creator: Aerojet-General Corporation
Object Type: Report
System: The UNT Digital Library
Army Gas-Cooled Reactor Systems Program Quarterly Progress Report: October 1 - December 31, 1964 (open access)

Army Gas-Cooled Reactor Systems Program Quarterly Progress Report: October 1 - December 31, 1964

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, 1965
Creator: Aerojet-General Corporation
Object Type: Report
System: The UNT Digital Library
Recommendations for exploration drilling, Lower Wild Horse Point, San Rafael Swell, Emery County, Utah (open access)

Recommendations for exploration drilling, Lower Wild Horse Point, San Rafael Swell, Emery County, Utah

The purpose of the investigation was to locate new uranium ore deposits and sites which are favorable for exploration drilling.
Date: December 15, 1952
Creator: Akright, Robert L.
Object Type: Report
System: The UNT Digital Library
Evaluation of Uranium Potential in Selected Pennsylvanian and Permian Units and Igneous Rocks in Southwestern and Southern Oklahoma: Enclosures for Final Report (open access)

Evaluation of Uranium Potential in Selected Pennsylvanian and Permian Units and Igneous Rocks in Southwestern and Southern Oklahoma: Enclosures for Final Report

This document consists of maps evaluating selected parts in Pennsylvania and rocks in Oklahoma.
Date: June 15, 1977
Creator: Al-Shaieb, Zuhair; Shelton, John W.; Donovan, R. Nowell; Hanson, Richard E. & May, Richard T.
Object Type: Report
System: The UNT Digital Library
Evaluation of Uranium Potential in Selected Pennsylvanian and Permian Units and Igneous Rocks in Southwestern and Southern Oklahoma: Final Report (open access)

Evaluation of Uranium Potential in Selected Pennsylvanian and Permian Units and Igneous Rocks in Southwestern and Southern Oklahoma: Final Report

Introduction: The areas of study include parts of the Wichita uplift, Arbuckle uplift, Hunton-Pauls Valley uplift, Central Oklahoma platform, Muenster-Waurika arch, and Anadarko basin (Fig. 1.1-1). Rocks examined include the Precambrian granite of the Arbuckle uplift, Cambrian igneous rocks of the Wichita uplift, and Pennsylvanian-Permian sedimentary rocks derived in large part from those two uplifts and, to a lesser extent, from the Ouachita system.
Date: June 15, 1977
Creator: Al-Shaieb, Zuhair; Shelton, John W.; Donovan, R. Nowell; Hanson, Richard E. & May, Richard T.
Object Type: Report
System: The UNT Digital Library
30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System: Volume 4, Operation and Maintenance Procedures (open access)

30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System: Volume 4, Operation and Maintenance Procedures

Operation and maintenance procedures for 30 megawatt heat exchanger and steam generator for sodium cooled reactor system.
Date: May 15, 1962
Creator: Alco Products (Firm)
Object Type: Report
System: The UNT Digital Library
Design Analysis of a Prepackaged Nuclear Power Plant for an Ice Cap Location (open access)

Design Analysis of a Prepackaged Nuclear Power Plant for an Ice Cap Location

Report describing a the design requirements of a proposed nuclear power plant for use on an ice cap.
Date: January 15, 1959
Creator: Alco Products (Firm)
Object Type: Report
System: The UNT Digital Library
Evaluation of Kanigen, Electroless Nickel Plating for Steam Side of a Sodium Component Steam Generator (open access)

Evaluation of Kanigen, Electroless Nickel Plating for Steam Side of a Sodium Component Steam Generator

Introduction: This is a final report on the evaluation of Kanigen electroless nickel plating for surfaces in contact with water and steam i a sodium heated AISI Type 316 stainless steel steam generator. The purpose of the coasting was to afford protection from stress corrosion cracking originating on the water-steam side of the unit. It has been concluded that the kanigen coating does not afford adequate protection for the services condition intended. This work was performed as part of the research and development program for the United States Atomic Energy Commission sodium Components Design Project.
Date: February 15, 1961
Creator: Alco Products (Firm).
Object Type: Report
System: The UNT Digital Library
Hot-Pressure Bonding of OMR Fuel Plates (open access)

Hot-Pressure Bonding of OMR Fuel Plates

Abstract: An alluminum-clad low-enrichment, uranium-alloy fuel element of flat plate configuration has been proposed for the Organic Moderated Reactor (OMR).
Date: November 15, 1959
Creator: Alm, G. V.; Binstock, M. H. & Garrett, E. E.
Object Type: Report
System: The UNT Digital Library
Effects of Ultraviolet Radiation on Chloroplast Reactions and Plant Metabolism (open access)

Effects of Ultraviolet Radiation on Chloroplast Reactions and Plant Metabolism

This technical report represents a brief survey of work by this project on the effects of ultraviolet radiation (UV) on certain of the photochemical and metabolic properties of rhubarb chard and sugar beet (Beta vulgaris). These plants were selected for this work because for some years they have been used as sources of chloroplasts for Hill reaction studies in this laboratory. Some of this work has appeared as a brief paper.
Date: June 15, 1955
Creator: Anderson, Donald R.; Spikes, John D. & Mayne, Berger C.
Object Type: Report
System: The UNT Digital Library
Analysis of Stresses in Bellows (open access)

Analysis of Stresses in Bellows

Abstract: Design charts and systematic design forms are presented for simplified calculations to check the number of convolutions and thickness required to limit the deflection and pressure stress range in three types of bellows.
Date: October 15, 1964
Creator: Anderson, W. F.
Object Type: Report
System: The UNT Digital Library
Chlorotriammineplatinum(II) Ion : Acid Hydrolysis and Isotopic Exchange of Chloride Ligand (open access)

Chlorotriammineplatinum(II) Ion : Acid Hydrolysis and Isotopic Exchange of Chloride Ligand

Abstract: The acid hydrolysis of [Pt(NH3)3Cl] has been shown to occur to a measurable extent. for this reaction: [APt(NH3)cCl]+ + H2O [chemical equilibrium symbol with rate constant k-1 above and k1 below] [Pt(NH3)c(H2O)]++ + Cl-, the equilibrium quotient was measured at 25 degree C and 35 degree C. At 25 degree C this quotient was 8.4 x 10-5 at [Mu] (ionic strength) = 0 and 25 x 10-5 at [mu] = .318 M. This variation is consistent with the expected changes in activity coefficients. [Delta]H for the reaction was found to be approximately 0. The rate constant, k1 was 2.3 x 10-5 sec.-1 at 25 degree C and it was nearly independent of ionic strength. The acid hydrolysis provides a mechanism for the exchange of the chloride ligand and Cl-. Exchange experiments with Cl36 showed that in addition to the acid hydrolysis, a process, first order in both, [Pt(NH3)3Cl] and Cl- with a rate constant of 6. 10-5 sec.-1M.-1 contributes to the exchange. The behavior of the entire series of chloro-ammines of platinum(II) toward acid hydrolysis and chloride exchange has been summarized, and a likely mechanism for the process has been discussed.
Date: May 15, 1961
Creator: Aprile, Ferruccio. & Martin, Don S., Jr.
Object Type: Report
System: The UNT Digital Library
Graphical Aids in the Calculation of the Shielding Requirements for Spent U²³⁵ Fuel (open access)

Graphical Aids in the Calculation of the Shielding Requirements for Spent U²³⁵ Fuel

Abstract: The data presented herein, in the form of graphs, can be used to obtain the value of this energy.
Date: November 15, 1957
Creator: Ashley, R. L.
Object Type: Report
System: The UNT Digital Library
Piqua Nuclear Power Facility Operations Analysis Program Progress Report Number 3: July-December 1963 (open access)

Piqua Nuclear Power Facility Operations Analysis Program Progress Report Number 3: July-December 1963

Progress report for the Piqua Reactor Operations Analysis Program describing observations and analyses at the Piqua Nuclear Power Facility (PNPF). The program goals are to monitor operations and collect data in order to ensure that the plant's operation is safe, to improve design and performance, to evaluate the performance and lifetime of the plant's components and systems, to evaluate plant safety and safeguards, and to disseminate all information to the scientific community.
Date: July 15, 1964
Creator: Auleta, J. J.
Object Type: Report
System: The UNT Digital Library
Criticality-Accident Dosimetry Studies (open access)

Criticality-Accident Dosimetry Studies

Experiments were carried out to (1) explore possibilities for developing a less expensive device than the Hurst threshold detector unit (TDU) for monitoring possible accidental critical reactions in uranium-processing facilities, (2) to study the precision and accuracy of the TDU, and (3) to evaluate the ORNL film badge in mixed neutron-gama radiation fields.
Date: October 15, 1964
Creator: Bailey, J. C.
Object Type: Report
System: The UNT Digital Library
The FAIM Code: a Multigroup, One-Dimensional Diffusion Equation Code (open access)

The FAIM Code: a Multigroup, One-Dimensional Diffusion Equation Code

Abstract: FAIM is a general multigroup, one-dimensional diffusion equation code programmed in FORTRAN language for the IBM 7090 computer.
Date: April 15, 1962
Creator: Baller, D. C.
Object Type: Report
System: The UNT Digital Library
Metallurgical Aspects of SRE Fuel Element Damage Episode (open access)

Metallurgical Aspects of SRE Fuel Element Damage Episode

Abstract: An investigation of the metallurgical aspects of the SRE fuel element episode, that occurred July 26, 1959, has been completed.
Date: October 15, 1961
Creator: Ballif, J. L.
Object Type: Report
System: The UNT Digital Library
Evaluation of Coolant Impurity Removal Equipment at the OMRE (open access)

Evaluation of Coolant Impurity Removal Equipment at the OMRE

Abstract: The experimental application of centrifugal clarification, precoat filtration, conventional filtration, and adsorption to the removal of impurities from a bypass stream of irradiated reactor coolant at the Organic Moderated Reactor Experiment is described and evaluated.
Date: October 15, 1964
Creator: Barbour, P. & Davis, W. W.
Object Type: Report
System: The UNT Digital Library
Interim Report of the Fuel Processing Group (open access)

Interim Report of the Fuel Processing Group

"This report covers mainly the work completed since the last interim report, HNL Log No. 0-4714. This report includes results from studies of the rare earth distribution in bismuth-uranium and fused chloride and studies of fused chloride behavior."
Date: January 15, 1952
Creator: Bareis, D. W.
Object Type: Report
System: The UNT Digital Library