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Large-Scale Slurry-Circulation System, 300-SM (open access)

Large-Scale Slurry-Circulation System, 300-SM

Design philosophy, status of component development, operational procedures, and limitations of each section of the Oak Ridge large-scale, high-temperature, thoria slurry facility.
Date: December 21, 1961
Creator: Parsly, L. F., Jr.; Falkenberry, H. L.; Harley, P. H.; Miller, I. M. & Kenyon, V. L.
System: The UNT Digital Library
Spectral Shift Control Reactor Design and Economic Study (open access)

Spectral Shift Control Reactor Design and Economic Study

Study of nuclear power plants incorporating the Spectral Shift Control Reactor (SSCR).
Date: December 1961
Creator: Mars, D. & Gans, D., Jr.
System: The UNT Digital Library
The Thermal Hydraulics Laboratory at Hanford (open access)

The Thermal Hydraulics Laboratory at Hanford

Report describing the experimental facilities of Hanford's Thermal Hydraulics Laboratory, its equipment, personnel, operating schedules, and safety procedures. Appendix begins on page 49.
Date: November 1961
Creator: Batch, J. M.; Toyoda, K. G. & Hanthorn, H. E.
System: The UNT Digital Library
Health Physics Division Annual Progress Report, July 31, 1961 (open access)

Health Physics Division Annual Progress Report, July 31, 1961

Report documenting research and developments made by the Health Physics Division of the Oak Ridge National Laboratory.
Date: October 31, 1961
Creator: Oak Ridge National Laboratory. Health Physics Division.
System: The UNT Digital Library
Evaluation of Ultimate Disposal Methods for Liquid and Solid Radioactive Wastes: Part 2, Conversion to Solid by Pot Calcination (open access)

Evaluation of Ultimate Disposal Methods for Liquid and Solid Radioactive Wastes: Part 2, Conversion to Solid by Pot Calcination

Economic and hazards calculation of pot calcination of Purex and Thorex wastes.
Date: October 16, 1961
Creator: Perona, J. J.; Bradshaw, R. L.; Roberts, J. T. & Blomeke, J. O.
System: The UNT Digital Library
Chemical Technology Division Annual Progress Report, May 31, 1961 (open access)

Chemical Technology Division Annual Progress Report, May 31, 1961

Report documenting the ongoing research and developments of the Chemical Technology Division of the Oak Ridge National Laboratory.
Date: September 21, 1961
Creator: Oak Ridge National Laboratory. Chemical Technology Division.
System: The UNT Digital Library
Failure Test of a Double Chambered NaK-Filled Irradiation Capsule (open access)

Failure Test of a Double Chambered NaK-Filled Irradiation Capsule

Report describing tests "in which a double chambered irradiation capsule containing NaK (sodium-potassium alloy) in its inner chamber was deliberately perforated to allow NaK (the heat transfer medium) and water to react within the capsule chambers" (p. 2). The report includes descriptions of the materials used in the tests, test procedures, and results.
Date: September 1961
Creator: Kosut, B. S.; Leggett, R. D. & Marshall, R. K.
System: The UNT Digital Library
Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1961 (open access)

Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1961

Report regarding the ongoing research and development related to the Army Gas-Cooled Reactor Systems Program. Includes status and progress of the program's projects, experiments, and data evaluations.
Date: August 10, 1961
Creator: Aerojet-General Corporation
System: The UNT Digital Library
Inline Densimeter for Pulsed Column Liquid Density Pulse Amplitude, and Pulse Frequency Measurements (open access)

Inline Densimeter for Pulsed Column Liquid Density Pulse Amplitude, and Pulse Frequency Measurements

Laboratory fabrication and testing of an inline densimeter.
Date: July 19, 1961
Creator: Mackey, T. S.
System: The UNT Digital Library
Numerical Results for EGCR Moderator-Element Stress Problems (open access)

Numerical Results for EGCR Moderator-Element Stress Problems

From introduction: "A recent report describes the development of a general program for the IBM Type 7090 electronic computer for calculating plane thermal stresses."
Date: July 3, 1961
Creator: Hulbert, Lewis E. & Redmond, Robert F.
System: The UNT Digital Library
The RBU Reactor-Burnup Code: Formulation and Operation Procedures (open access)

The RBU Reactor-Burnup Code: Formulation and Operation Procedures

Report discussing the computer program RBU, which calculates the neutron, reactivity, and isotopic history of a nuclear reactor in such a way as to facilitate the predictions of fuel costs and reactor performance. This report documents RBU's various calculations and operating procedures.
Date: July 1961
Creator: Triplett, J. R.; Merrill, E. T. & Burr, J. R.
System: The UNT Digital Library
Molten-Salt Reactor Program Progress Report, August 1, 1960 to February 28, 1961 (open access)

Molten-Salt Reactor Program Progress Report, August 1, 1960 to February 28, 1961

Report containing ongoing projects and experiments undertaken by the Oak Ridge National Laboratory's Molten-Salt Reactor Program.
Date: June 27, 1961
Creator: Oak Ridge National Laboratory
System: The UNT Digital Library
Economic Evaluation of a 300-Mw(e) Supercritical Pressure Power Reactor (open access)

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
Heat Transfer Calculations for the PRTR Pressurized Gas-Cooled Loop Facility (open access)

Heat Transfer Calculations for the PRTR Pressurized Gas-Cooled Loop Facility

A series of calculations are described which evaluated the heat transfer and fluid flow aspects of the Plutonium Recycle Test Reactor Pressurized Gas-Loop Facility.
Date: June 1961
Creator: Muraoka, J.
System: The UNT Digital Library
Metallographic Study of the Annealing Behavior of Aluminum-Silicon Eutectic Alloy (open access)

Metallographic Study of the Annealing Behavior of Aluminum-Silicon Eutectic Alloy

This purpose of this report is to establish a means of determining the mean effective temperature at which any specimen of Al-Si had been annealed.
Date: June 1961
Creator: Todd, R. H.
System: The UNT Digital Library
Thermonuclear Division Semiannual Progress Report, January 31, 1961 (open access)

Thermonuclear Division Semiannual Progress Report, January 31, 1961

Report describing ongoing progress made at the Oak Ridge National Laboratory's Thermonuclear Division.
Date: May 31, 1961
Creator: Oak Ridge National Laboratory
System: The UNT Digital Library
Polfit II, an IBM 7090 Program for Polynomial Least Squares Fitting (open access)

Polfit II, an IBM 7090 Program for Polynomial Least Squares Fitting

Program written to perform polynomial least squares fits on the the IBM 7090 computer.
Date: April 24, 1961
Creator: Lietzke, M. P.
System: The UNT Digital Library
Fabrication Development of UO2-Stainless Steel Composite Fuel Plates for core B of the Enrico Fermi Fast Breeder Reactor (open access)

Fabrication Development of UO2-Stainless Steel Composite Fuel Plates for core B of the Enrico Fermi Fast Breeder Reactor

Experimental work concerned with the development of an inexpensive composite fuel plate with a high burnup potential for application in a 500°C sodium environment as Core B of the Enrico Fermi Fast Breeder Reactor.
Date: April 18, 1961
Creator: Cherubini, J. H.; Beaver, R. J. & Leitten, C. F., Jr.
System: The UNT Digital Library
Mathematics Panel: Annual Progress Report for Period Ending December 31, 1960 (open access)

Mathematics Panel: Annual Progress Report for Period Ending December 31, 1960

Programming research in the construction of a translator to Oracle language from ALGOL.
Date: April 6, 1961
Creator: unknown
System: The UNT Digital Library
Sulfex Process: Engineering-Scale Semicontinuous Decladding of Unirradiated Stainless Steel-Clad UO2 and UO2-ThO2 (open access)

Sulfex Process: Engineering-Scale Semicontinuous Decladding of Unirradiated Stainless Steel-Clad UO2 and UO2-ThO2

An engineering-scale demonstration of the Sulfex process indicated that semi-continuous decladding of unirradiated stainless steel-clad UO2 or U02ThO2 fuels is feasible.
Date: April 4, 1961
Creator: Finney, B. C. & Hannaford, B. A.
System: The UNT Digital Library
Pneumatic Injection Casting of Aluminum-Plutonium Fuel Elements (open access)

Pneumatic Injection Casting of Aluminum-Plutonium Fuel Elements

This report summarizes only that portion of the injection-casting experiments in which the castings were made with air pressure.
Date: April 1961
Creator: Koler, R. K.
System: The UNT Digital Library
Final Design Report: DR-1 Gas Loop (open access)

Final Design Report: DR-1 Gas Loop

Report describing the performance, fission product tolerance, design, and costs of the DR-1 Gas Loop, which is an in-reactor test facility.
Date: March 1961
Creator: Baars, R. E.
System: The UNT Digital Library
Plutonium Spike Fuel Elements for the Plutonium Recycle Test Reactor: Part 1 - The Mark 1-G (open access)

Plutonium Spike Fuel Elements for the Plutonium Recycle Test Reactor: Part 1 - The Mark 1-G

Report describing "[t]he fabrication of of the first aluminum-plutonium spike enrichment fuel elements for the Plutonium Recycle Test Reactor (PRTR) at Hanford" Laboratory (p. 2).
Date: March 1961
Creator: Freshley, M. D.
System: The UNT Digital Library
Plutonium Spike Fuel Elements for the Plutonium Recycle Test Reactor: Part 2 - The Mark 1-H (open access)

Plutonium Spike Fuel Elements for the Plutonium Recycle Test Reactor: Part 2 - The Mark 1-H

Report describing the fabrication of of the I-H aluminum-plutonium spike enrichment fuel elements for the Plutonium Recycle Test Reactor (PRTR), including the materials used and design specifications. Appendix begins on page 28.
Date: March 1961
Creator: Sharp, R. E.
System: The UNT Digital Library