Ionic Equilibria and Anion Exchange of Uranyl Sulfate Solutions (open access)

Ionic Equilibria and Anion Exchange of Uranyl Sulfate Solutions

Theoretical investigation on the nature of ion exchange of acidified uranyl sulfate solutions with Dowex 21K, a strong base ion exchange resin.
Date: September 28, 1962
Creator: Stein, P. E.
System: The UNT Digital Library
Evaluation of Beta Radiation as a Hydrogenation Catalyst: Interim Technical Status Report for the Period March 1, 1962 to October 31, 1963 (open access)

Evaluation of Beta Radiation as a Hydrogenation Catalyst: Interim Technical Status Report for the Period March 1, 1962 to October 31, 1963

From abstract: The concept of using high intensity beta radiation from an isotopic source, Sr-90, inside a high temperature, high pressure chemical reactor has been developed for potential radiation chemical processes. Distinct advantages include high utilizable intensity from a relatively small source with a minimum of shielding against external radiation.
Date: September 11, 1964
Creator: Yavorsky, P. M. & Gorin, E.
System: The UNT Digital Library
A Study of Desalting Plants (15 to 150 mgd) and Nuclear Power Plants (200 to 1500 MWt) for Combined Water and Power Production: Final Report (open access)

A Study of Desalting Plants (15 to 150 mgd) and Nuclear Power Plants (200 to 1500 MWt) for Combined Water and Power Production: Final Report

From foreword: This study is concerned with the technology of producing fresh potable water from the seas.
Date: September 1964
Creator: Catalytic Construction Company
System: The UNT Digital Library
Coolant Flow and Outlet Temperature: Computer-Monitors for the Hallam Nuclear Power Facility Plant Protective System (open access)

Coolant Flow and Outlet Temperature: Computer-Monitors for the Hallam Nuclear Power Facility Plant Protective System

Abstract: The design and application of two computers for the HNPF protective system is discussed.
Date: September 15, 1961
Creator: Schlein, H.
System: The UNT Digital Library
Steam-Cooled Power Reactor Evaluation: Graphite-Moderated, Boiling Water, Steam-Superheat Reactor (open access)

Steam-Cooled Power Reactor Evaluation: Graphite-Moderated, Boiling Water, Steam-Superheat Reactor

Abstract: A conceptual reference design of a 318 Mw(e) Graphite Moderated Boiling and Superheating Reactor (GBSR) is described.
Date: September 1961
Creator: unknown
System: The UNT Digital Library
A Multichannel Digital Recording System (open access)

A Multichannel Digital Recording System

Abstract: This report is a description of a 200 channel digital recording system used to record high temperature strain gage outputs and associated temperatures.
Date: September 15, 1960
Creator: Truitt, R. W.
System: The UNT Digital Library
High Temperature Corrosion of Some Metals and Ceramics in Fluorinating Atmospheres (open access)

High Temperature Corrosion of Some Metals and Ceramics in Fluorinating Atmospheres

Abstract: The results of this investigation leave little doubt that diffusion of the fluorinating gas along the grain boundaries of the nickel fluoride film to react at the metal-scale interface is the primary mechanism of attack upon pure nickel and its more promising alloys.
Date: September 30, 1960
Creator: Hale, C. F.; Barber, E. J.; Bernhardt, H. A. & Rapp, Karl E.
System: The UNT Digital Library
Reactor Technology Report Number 22: Chemistry (open access)

Reactor Technology Report Number 22: Chemistry

Quarterly report issued by the Knolls Atomic Power Laboratory to report to the industry on developments in unclassified reactor technology. This issue focuses on chemistry information.
Date: September 1962
Creator: unknown
System: The UNT Digital Library
Carbide Fuels in Fast Reactors (open access)

Carbide Fuels in Fast Reactors

Abstract: Cladding and fuel material processing prospects are reviewed, and fuel system possibilities for near-term (~1 mill/kwh) and long-range (<0.5 mil/kmh) fuel cycles are described.
Date: September 15, 1965
Creator: Wheelock, C. W.
System: The UNT Digital Library
Stress and Elevated Temperature Fatigue Characteristics of Large Bellows (open access)

Stress and Elevated Temperature Fatigue Characteristics of Large Bellows

From abstract: Charts in this report show axial stress distribution over exterior bellows surfaces induced by bellows axial deflection, and by internal pressurization. The influence of root rings on stress distribution is presented graphically.
Date: September 15, 1964
Creator: Winborne, R. A.
System: The UNT Digital Library
Hallam Nuclear Power Facility, Reactor Operations Analysis Program: Semiannual Progress Report Number 3, September 1963-February 1964 (open access)

Hallam Nuclear Power Facility, Reactor Operations Analysis Program: Semiannual Progress Report Number 3, September 1963-February 1964

From introduction: This report provides industry, plant operators, and the scientific community with information covering the results of the performance analysis.
Date: September 15, 1964
Creator: Darley, D. K.
System: The UNT Digital Library
Quarterly Progress Report, Research and Development Activities Fixation of Radioactive Residues: April-June 1965 (open access)

Quarterly Progress Report, Research and Development Activities Fixation of Radioactive Residues: April-June 1965

Introduction: "This progress report is the twenty-sixth in a series presenting research and development activities in the field of radioactive wastes. Experimental work charged to programs other than those of the Division of Reactor Development is included for general interest and completeness; such work is identified in the headings."
Date: September 1965
Creator: Pacific Northwest Labortoary. Chemistry Department.
System: The UNT Digital Library
The Flora of Healthy Dogs: [Part] 1. Bacteria and Fungi of the Nose, Throat, and Lower Intestine (open access)

The Flora of Healthy Dogs: [Part] 1. Bacteria and Fungi of the Nose, Throat, and Lower Intestine

Report documenting the isolation and identification of microorganisms found in the noses, throats, and lower intestines of twenty two dogs. The most frequently observed organisms were E. coli and S. viridans.
Date: September 1962
Creator: Clapper, W. E. & Meade, G. H.
System: The UNT Digital Library
Accurate Nuclear Fuel Burnup Analysis Quarterly Progress Report: Seventh Quarter, June 1963 - August 1963 (open access)

Accurate Nuclear Fuel Burnup Analysis Quarterly Progress Report: Seventh Quarter, June 1963 - August 1963

Quarterly progress report on Accurate Nuclear Fuel Burnup Analysis project.
Date: September 1, 1963
Creator: Rider, B. F.; Ruiz, C. P.; Peterson, J. P., Jr.; Luke, P. S., Jr. & Smith, F. R.
System: The UNT Digital Library
Two-Phase Pressure Losses Quarterly Progress Report: Sixth Quarter, May 12, 1963 - August 12, 1963 (open access)

Two-Phase Pressure Losses Quarterly Progress Report: Sixth Quarter, May 12, 1963 - August 12, 1963

Technical report describing that the pressure drops along 3/4-inch, 1-inch, and 1-1/4 inch straight pipes and across three contraction-expansion inserts in a 1-inch pipe have been measured under both single- and two-phase flow conditions. Pressure was varied from 600 to 1400 psia, flow from 0.25 x 10(6) to 1.66 x 10(6) lb/hr ft, and quality from zero to 90 percent. The single-phase pipe friction factor agrees with the Moody value for smooth pipe. The two-phase friction for horizontal flow shows no size effect in the range of pipe sizes from 3/4 inch to 1-1/4 inch. The values lie below the Martinelli curve at the lower qualities (x<0.6), but at high qualities tend to be above the Martinelli curve. The single-phase loss coefficient for the three contraction-expansion inserts show very little Reynolds number effect in the range of channel Reynolds numbers from 3 x 10(4) to 5 x 10(5). The two-phase data for insert number 1 has not yet been reduced. The two-phase loss for insert numbers 2 and 3 lies generally below the loss prediction based on a homogeneous flow model. The two-phase loss for insert number 2 shows excellent agreement with the corresponding loss for the S-1 insert in …
Date: September 1, 1963
Creator: Janssen, E. (Engineer) & Kervinen, J. A.
System: The UNT Digital Library
Full Power and Limited Endurance Test of the ML-1 Nuclear Power Plant (ANSOP 16625A) (open access)

Full Power and Limited Endurance Test of the ML-1 Nuclear Power Plant (ANSOP 16625A)

Report presenting "[t]he results of performance analyses of the ML-1 nuclear power plant based on the test data obtained during ANSOP 16625A" (p. v).
Date: September 1964
Creator: Aerojet-General Corporation
System: The UNT Digital Library
Chemical Technology Division Annual Progress Report, May 31, 1968 (open access)

Chemical Technology Division Annual Progress Report, May 31, 1968

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: September 1968
Creator: Oak Ridge National Laboratory. Chemical Technology Division.
System: The UNT Digital Library
Chemical Technology Division Annual Progress Report: for Period Ending June 30, 1962 (open access)

Chemical Technology Division Annual Progress Report: for Period Ending June 30, 1962

Report issued by Oak Ridge National Laboratory that discusses progress and work performed by the Chemical Technology Division.
Date: September 21, 1962
Creator: Oak Ridge National Laboratory. Chemical Technology Division.
System: The UNT Digital Library
Chemical Technology Division Annual Progress Report: for Period Ending May 31, 1963 (open access)

Chemical Technology Division Annual Progress Report: for Period Ending May 31, 1963

Report issued by Oak Ridge National Laboratory that describes research and progress at the Chemical Technology Division.
Date: September 20, 1963
Creator: Oak Ridge National Laboratory. Chemical Technology Division.
System: The UNT Digital Library
Metallurgy Division Annual Progress Report, July 1, 1960 (open access)

Metallurgy Division Annual Progress Report, July 1, 1960

Report documenting ongoing research and development undertaken by the Metallurgy Division of the Oak Ridge National Laboratory.
Date: September 30, 1960
Creator: Oak Ridge National Laboratory. Metallurgy Division.
System: The UNT Digital Library
Experimental Breeder Reactor-II (EBR-II) Shield Design (open access)

Experimental Breeder Reactor-II (EBR-II) Shield Design

Report describing the EBR-II shield and the methods employed in arriving at the final design. The major shield design problems for that reactor are enumerated and discussed.
Date: September 1962
Creator: Grotenhuis, M.; McArthy, A. E. & Rossin, A. D.
System: The UNT Digital Library
The Graetz Problem in Cocurrent-Flow, Double-Pipe, Heat Exchangers (open access)

The Graetz Problem in Cocurrent-Flow, Double-Pipe, Heat Exchangers

Report showing "that the Graetz Problem pertaining to the cocurrent-flow, double-pipe, heat exchanger can be studied analytically by extensions of familiar mathematical techniques" (p. 7).
Date: September 1964
Creator: Stein, Ralph P.
System: The UNT Digital Library
Nuclear Superheat Quarterly Project Report: Second Quarter, October-December 1959 (open access)

Nuclear Superheat Quarterly Project Report: Second Quarter, October-December 1959

From introduction: "This is the second of a series of quarterly reports which will cover the progress and results from the conceptual design, economic evaluations and research and development work performed by the General Electric Company as part of the Nuclear Superheat Project."
Date: September 1960
Creator: U.S. Atomic Energy Commission
System: The UNT Digital Library
Nuclear Superheat Quarterly Project Report: Fifth Quarter, July-September 1960 (open access)

Nuclear Superheat Quarterly Project Report: Fifth Quarter, July-September 1960

From introduction: "this is the fifth of a series of quarterly reports which will cover the progress and results from the conceptual design, economic evaluations and research and development work performed by the General Electric Company as part of the Nuclear Superheat Project."
Date: September 1961
Creator: U.S. Atomic Energy Commission
System: The UNT Digital Library