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Analytical Chemistry Division Annual Progress Report, December 31, 1960
Report presenting research and development papers from the Oak Ridge National Laboratory's Analytical Chemistry Division.
Date:
1961
Creator:
Oak Ridge National Laboratory
System:
The UNT Digital Library
Corn Pone: A Multigroup, Multiregion Reactor Code
Report covering the development of a set of difference equations for machine solution. In addition, this report serves as user's manual for Corn Pone, which is a code for the Oracle, the Oak Ridge National Laboratory computer.
Date:
1961?
Creator:
Kinney, W. E. & Coveyou, R. R.
System:
The UNT Digital Library
Experimental Stress Analysis of EGCR Pressure Vessel
Report regarding the structural evaluations made of the upper head of the Experimental Gas Cooled Reactor (EGCR). This report includes descriptions of the model, experimental procedures, and analyses of the results. Appendix begins on page 139.
Date:
1961
Creator:
Greenstreet, B. L.; Holland, R. W.; Maxwell, R. L.; Witt, F. J.; Shobe, L. R. & LaVerne, M. E.
System:
The UNT Digital Library
Gas-Cooled Reactor Project Quarterly Progress Report: December 1960
Report documenting the research and development of the Oak Ridge National Laboratory's Gas-Cooled Reactor Project.
Date:
1961
Creator:
Oak Ridge National Laboratory
System:
The UNT Digital Library
Gas-Cooled Reactor Project Quarterly Progress Report: March 1961
Report documenting ongoing research and developments at the Oak Ridge National Laboratory's Gas-Cooled Reactor Project.
Date:
1961
Creator:
Oak Ridge National Laboratory
System:
The UNT Digital Library
Gas-Cooled Reactor Project Quarterly Progress Report: June 1961
Report documenting the ongoing research and developments at the Oak Ridge National Laboratory's Gas-Cooled Reactor Program.
Date:
1961
Creator:
Oak Ridge National Laboratory
System:
The UNT Digital Library
Gas-Cooled Reactor Project Quarterly Progress Report: September 1961
Report containing the ongoing research and developments at the Oak Ridge National Laboratory's Gas-Cooled Reactor Program.
Date:
1961
Creator:
Oak Ridge National Laboratory
System:
The UNT Digital Library
Superposition of Forced and Diffusive Flow in a Large-Pore Graphite
Report describing an "investigation of steady-state counter-flow of gases in a large pore graphite" by exposing it to streams of helium and argon.
Date:
1961
Creator:
Evans, R. B., III; Truitt, J. & Watson, G. M.
System:
The UNT Digital Library
Health and Safety Laboratory Fallout Program Quarterly Summary Report: September 1, 1960 - December 1, 1960
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:
January 9, 1961
Creator:
Hardy, Edward P., Jr.; Rivera, Joseph & Frankel, Robert
System:
The UNT Digital Library
Evaluation of Iron- and Nickel-Base Alloys for Medium and High Temperature Reactor Applications, Part 1
Report discussing the evaluation of the "behavior of austenitic and ferritic stainless steels, iron-chromium-aluminum base alloys and nickel-base superalloys, in medium and high temperature simulated reactor environments" (p. 2).
Date:
February 1961
Creator:
Pessl, H. J.
System:
The UNT Digital Library
Supplemental Report on New Production Reactor Power Plant Economic Feasibility Study: Volume 1-S
From purpose and scope of study: This report contains a primary study based on estimated loads and resources deemed most likely to occur and a secondary study based on the sale by the summer of 1961 of an additional 400 MW of power to industries resulting in an equal increase in loads.
Date:
February 1961
Creator:
unknown
System:
The UNT Digital Library
Oak Ridge National Laboratory Intrumentation and Controls Division Annual Progress Report: 1960
Report containing ongoing research and experiments of the Oak Ridge National Laboratory's Instrumentation and Controls Division.
Date:
February 3, 1961
Creator:
Oak Ridge National Laboratory. Instrumentation and Controls Division.
System:
The UNT Digital Library
Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: July 1 - December 31, 1960
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 22, 1961
Creator:
Aerojet-General Corporation
System:
The UNT Digital Library
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
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
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
A Report on Some Attempts to Cast Centrifugally Fuel Elements of Small Diameter
Report issued by the Argonne national Laboratory discussing centrifugal casting of thin uranium plates. The applicability of the centrifugal casting technique to the production of multiple castings of fuel pins of small diameter and of thin fuel plates was investigated. This report includes tables, illustrations, and photographs.
Date:
March 1961
Creator:
Yaggee, F. L.
System:
The UNT Digital Library
The Cold Pressing of Sinterable UO₂
The intent of this work was to explore more fully the pressing of sinterable UO2 powders into cylindrical compacts in the hope that a more precise prediction of green density in terms of powder properties, pressure, and geometry could be evolved.
Date:
March 27, 1961
Creator:
Levey, R. P., Jr.
System:
The UNT Digital Library
Health and Safety Laboratory Fallout Program Quarterly Summary Report: December 1, 1960 - March 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:
April 1, 1961
Creator:
Hardy, Edward P., Jr.; Rivera, Joseph & Frankel, Robert
System:
The UNT Digital Library
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
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
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
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
A Study of the Feasibility of a Small Scale Reprocessing Plant for the Dresden Nuclear Power Station
Report describing the design, feasibility, and economic concerns of a small-scale reprocessing plant.
Date:
April 28, 1961
Creator:
Schneider, H.; Fletcher, R. D.; Codding, J. W.; Bearden, R. G.; Erickson, E. E.; Horn, S. J. et al.
System:
The UNT Digital Library