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Health and Safety Laboratory Fallout Program Quarterly Summary Report: September 1, 1961 - December 1, 1961
Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.
Date:
December 30, 1961
Creator:
Hardy, Edward P., Jr.; Rivera, Joseph & Frankel, Robert
System:
The UNT Digital Library
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
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
Status of the Application of Nuclear Reactors in the Process Industries: 1961
From preface: This report is a detailed summary of the evaluation studies of civilian power reactor concepts. It is intended to present the current state of the use of nuclear reactors in process industries and current AEC program in this field.
Date:
December 1961
Creator:
unknown
System:
The UNT Digital Library
The Influence of Design and Production Parameters on Fabrication Costs of Nuclear Reactor Fuel Elements
The objectives for this study were to determine fuel fabrication and assembly costs in a large nuclear power industry for several reactors, fuel rod sizes, and fuel materials.
Date:
November 1, 1961
Creator:
Stein, P. E.; Ayers, A. C.; Braatz, R. J.; Bradford, C. M.; Holt, V. D. & Mattie, G. P.
System:
The UNT Digital Library
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
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
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
An Evaluation of Reactor Concepts for Use As Separate Steam Superheaters
Report estimating the merits of a variety of nuclear reactor concepts for use as external superheaters to be added on to a steam-producing nuclear power plant.
Date:
October 1961
Creator:
Lennox, D. H.; MacFarlane, D. R.; Brubaker, R. C.; Martinec, E. L.; Rohde, R. R.; Toppel, B. J. et al.
System:
The UNT Digital Library
Health and Safety Laboratory Fallout Program Quarterly Summary Report: June 1, 1961 - September 1, 1961
Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.
Date:
October 1, 1961
Creator:
Hardy, Edward P., Jr.; Rivera, Joseph & Frankel, Robert
System:
The UNT Digital Library
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
The Design, Installation, and Testing of the Gas-Cooled Reactor UOâ‚‚ Irradiation Experiment at the NRTS
Report regarding sixteen experiments performed with a miniature re-entrant gas loop. Includes design problems and difficulties encountered, as well as their solutions.
Date:
September 8, 1961
Creator:
Porter, E. H.
System:
The UNT Digital Library
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
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
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
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
Health and Safety Laboratory Fallout Program Quarterly Summary Report: March 1, 1961 - June 1, 1961
Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.
Date:
July 1, 1961
Creator:
Hardy, Edward P., Jr.; Rivera, Joseph & Frankel, Robert
System:
The UNT Digital Library
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
Engineering Evaluation Studies: Heavy Water Moderated Power Reactor Plants
Foreword: This report describes results of a series of evaluation and design studies conducted between July 1, 1960 and June 30, 1961, related to heavy water moderated power reactor plants.
Date:
June 30, 1961
Creator:
Chittenden, W. A. & Hoveke, G. F.
System:
The UNT Digital Library
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
Engineering Test Reactor Critical Facility Control System Manual
This report consists of the description, drawings, connections, and schematics of the various control elements that make up the control system of the Engineering Test Reactor Critical Facility (ETRC).
Date:
June 23, 1961
Creator:
Meichle, F. A.
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
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
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