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Location of Orbital Axis in Table-Top Stellarator
This report discusses what effects the shift of an orbital axis relative to the center of the table-top stellarator tube as well as the magnitude of these effects.
Date:
June 9, 1952
Creator:
Spitzer, Lyman, Jr.
System:
The UNT Digital Library
The Shielding of Mobile Reactors - [Part] 2
From abstract: "The methods of applying results of bulk-shielding measurements to the design of reactor shields is outlined. Geometrical transformations for the more common shapes are derived, as are approximate means of calculating leakage of radiation. As an illustration of the methods, the ORNL Lid Tanks and Bulk Shielding Facility data are transformed to a standard geometry and compared. Two direct calculations of water attenuation, using cross sections described in the previous article, are finally compared with the experimental data."
Date:
June 30, 1952
Creator:
Blizard, E. P. & Welton, T. A.
System:
The UNT Digital Library
Preliminary report on exploration in the Atkinson Mesa area, Montrose County, Colorado
A preliminary report regarding exploration in the Atkinson Mesa Area, Montrose County, Colorado
Date:
June 1953
Creator:
Brew, David A.
System:
The UNT Digital Library
The Spectrophotometric Determination of Boron in Plutonium Using an Oxalate Separation
An improved method for the determination of boron in plutonium is reported. Precipitation of plutonium (III) acid oxalate prior to color development with curcumin results in increased precision, greater speed, and lower costs. Results are presented of a statistical study involving all variables.
Date:
June 25, 1953
Creator:
Newell, Donald M.
System:
The UNT Digital Library
Evaluation and Consolidation of Electrolytic Thorium
Abstract: "Sound, fabricable ingots of thorium were produced by triple are melting of electrolytic thorium. Consumable electrodes were fabricated by tack welding of cold-pressed and vacuum-sintered bars of the granular thorium electrodeposited from a molten-salt bath. The hydrogen content of the electrodeposited material was reduced from 80 to 4 ppm by vacuum sintering at 1250 C at pressures below 1 x 10-(-3) mm of mercury. Both sodium and chlorine content were reduced during melting; sodium from 250 to 25 ppm and chlorine from 1000 to 30 ppm. Oxygen and HCl acid-insoluble contents increased during sintering and melting. Oxygen content increased from 0.35 to 0.50 w/o and HCl acid-insoluble content from 0.8 to 4.0 w/o. A starlike includion revealed by metallographic examination of the as-cast thorium was identified as ThO2."
Date:
June 15, 1955
Creator:
Saller, Henry A.; Dickerson, Ronald F. & Foster, Ellis L.
System:
The UNT Digital Library
Ceramic Investigations of UO₂
This report covers the progress made on an intensive program to develop and evaluate UO2 as a possible fuel element for the PWR.
Date:
June 16, 1955
Creator:
Allison, Adrian G. & Duckworth, Winston H.
System:
The UNT Digital Library
A Continuous Water Monitor for Detecting PPM Quantities of Alkali Metals
Abstract: "This report describes a flame photometric system which continuously monitors a process water stream for ppm quantities of alkali metals, and automatically diverts the stream when the contamination exceeds a pre-determined level."
Date:
June 20, 1955
Creator:
Been, Julian F.
System:
The UNT Digital Library
Health Physics Report: October-December 1957
Summary: A survey was made of KAPL personnel currently exposed to radiation relating to their previous work with radiation or radioactive materials.
Date:
June 4, 1958
Creator:
unknown
System:
The UNT Digital Library
Plutonium Recycle Test Reactor Preliminary Safeguards Analysis
Report describing the Hanford Atomic Works' Plutonium Recycle Test Reactor, its siting concerns, operation, and safety concerns.
Date:
June 5, 1958
Creator:
Wittenbrock, N. G.
System:
The UNT Digital Library
Argonne High-Flux Research Reactor: AHFR Conceptual Design Study
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.
System:
The UNT Digital Library
Transistorized Log-Period Amplifier
Abstract: A log-period amplifier which is combined with power supply on a rack-mounted chassis with a 7-in. panel is described.
Date:
June 1959
Creator:
Wade, E. J. & Davidson, D. S.
System:
The UNT Digital Library
Physics Division Annual Progress Report, March 10, 1959
Report containing reports from the Physics Division of the Oak Ridge National Laboratory that cover a wide variety of subjects.
Date:
June 10, 1959
Creator:
Oak Ridge National Laboratory. Physics Division.
System:
The UNT Digital Library
Oak Ridge National Laboratory Instrumentation and Controls Division Annual Progress Report: 1958
Report documenting ongoing research and development carried out by the Instrumentation and Controls Division of the Oak Ridge National Laboratory.
Date:
June 24, 1959
Creator:
Oak Ridge National Laboratory. Instrumentation and Controls Division.
System:
The UNT Digital Library
Molten-Salt Reactor Program Quarterly Progress Report: April 1959
Report documenting ongoing experiments, designs, and tests undertaken by the Oak Ridge National Laboratory for the Molten-Salt Reactor Project.
Date:
June 26, 1959
Creator:
Oak Ridge National Laboratory
System:
The UNT Digital Library
Engineering Evaluation of a Mixed Alloy Fuel Element Irradiated at Elevated Temperatures in the SRE
Abstract: A fuel material evaluation was made by destructively examining a full-scale experimental fuel element, irradiated in the SRE to a maximum of 850 Mwd/MTU.
Date:
June 1, 1960
Creator:
Ballif, J. L.; Hayward, B. R. & Walter, J. W.
System:
The UNT Digital Library
Investigation of Types of Seals for Main Coolant Pumps for Large Pressurized Water Reactor Nuclear Plants
From introduction: This report sets forth the results of a study of canned-motor and controlled-leakage pumps for large pressurized water reactor nuclear plants.
Date:
June 1960
Creator:
unknown
System:
The UNT Digital Library
Reactor Technology Report Number 13: Engineering
Quarterly report issued by the Knolls Atomic Power Laboratory to report to the industry on developments in unclassified reactor technology. This issue focuses on engineering information.
Date:
June 1960
Creator:
unknown
System:
The UNT Digital Library
Description of the Thermal Hydraulics Laboratory at Hanford
Report describing the thermal hydraulics facilities at Hanford Laboratories as well as its operation, equipment, and systems.
Date:
June 2, 1960
Creator:
Batch, J. M. & Toyoda, K. G.
System:
The UNT Digital Library
Semi Works Studies for the Reduction of Corrosion-Product Impurities in UR-Plant UO3
This report describes the work carried out in 321 Building semiworks equipment, to define the factors contributing to high corrosion-product contamination and presents recommendations for reducing the impurity level to meet current specifications (maximum of 200 parts total metals per million parts U).
Date:
June 14, 1960
Creator:
Amos, L. C.; Kirkendall, B. E. & Adler, K. L.
System:
The UNT Digital Library
Stability of Phosphors to Beta Radiation
From foreword: This report presents the results of a study on the stability of phosphors under high energy beta radiation.
Date:
June 24, 1960
Creator:
Senett, W. P.; Diehl, K. & Wright, R.
System:
The UNT Digital Library
Boiling Songs and Associated Mechanical Vibrations
From introduction: The study is based entirely on observations which have been made at a number of different installations at which boiling songs and vibrations were noted during heat transfer experiments.
Date:
June 30, 1960
Creator:
Firstenberg, H.
System:
The UNT Digital Library
Design Evaluation and Comparison 200 MWe Boiling D₂O Pressure Tube Indirect and Direct Cycle Power Reactor Plants
From foreword: This report is concerned with the investigation of an indirect cycle plant which was the subject of a joint study between Sargent & Lundy and NDA.
Date:
June 30, 1960
Creator:
unknown
System:
The UNT Digital Library
OMR (Piqua) Unitized Control-Safety Rod Prototype Tests
Abstract: A unitized magnetic jack driven control-safety rod has been developed for the 45.5 thermal megawatt organic moderated reactor (Piqua).
Date:
June 30, 1960
Creator:
Howell, J. D. & Weeks, C. C.
System:
The UNT Digital Library
Economic Evaluation of a 300-Mw(e) Supercritical Pressure Power Reactor
Report describing a 300-Mw(e) Supercritical Pressure Power Reactor's facilities, physics, economics, and problems encountered during its development. Appendix begins on page 103.
Date:
June 1961
Creator:
Harty, H.; Regimbal, J. J.; Toyoda, K. G. & Widrig, R. D.
System:
The UNT Digital Library