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Health and Safety Laboratory Environmental Quarterly Report: June 1, 1977 - September 1, 1977
Report that presents information regarding chemical and radioactive pollution in the world. Includes tabulations of radionuclides and lead in milk, food, and tapwater.
Date:
October 1, 1977
Creator:
Hardy, Edward P., Jr.
System:
The UNT Digital Library
Health and Safety Laboratory Environmental Quarterly Report: October 1, 1977, Appendix
Report that presents information regarding chemical and radioactive pollution in the world. This appendix includes a quarterly report of the deposition of strontium-90 and measurements of radionuclides and lead in surface air, milk, and tapwater. Includes a table of radionuclides.
Date:
October 1, 1977
Creator:
HASL (New York, N.Y.)
System:
The UNT Digital Library
In-Pile Test of Prototype ML-1 Fuel Elements
Report documenting the testing of prototype fuel elements used in a mobile nuclear power plant. Includes descriptions and evaluations of the test.
Date:
June 1964
Creator:
Brunhouse, J. S.; Burgess, A. B.; Geering, G. T.; Nakazato, S. & Titus, G. W.
System:
The UNT Digital Library
Preliminary Designs for Four Integrated Gas-Cooled Ceramic-Fueled and -Moderated Reactor Core and Steam Generator Units
Report containing preliminary designs for four reactor core and steam generator units. The units, their difficulties, and the layout of the reactor building are described.
Date:
1962
Creator:
Fraas, A. P.
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
Calculation of Suspension Peptization
Report regarding the combination the theories of flocculation, particle repulsion, and particle attraction in order to "understand the flocculation characteristics of TH02 suspensions" (p. 2).
Date:
1960
Creator:
Sweeton, F. H.
System:
The UNT Digital Library
Laboratory Development of a Tributyl Phosphate Solvent Extraction Process for Processing 20% Enriched Uranium Alloy Fuel
Report containing a preliminary chemical flowsheet "for the preparation of feed and two solvent extraction cycles for the processing of silicon-containing aluminum-uranium alloy, 20% enriched, fuel elements" (p. 2).
Date:
1961
Creator:
Goode, J. H. & Flanary, J. R.
System:
The UNT Digital Library
Applied Health Physics Annual Report for 1963
Report issued by the Oak Ridge National Laboratory discussing work and progress made by the Health and Physics Division during 1963. Instrumentation, personnel monitoring, and laboratory monitoring is presented. This report includes maps, tables, illustrations, and photographs.
Date:
August 1964
Creator:
Morgan, K. Z.; Davis, D. M.; Hart, J. C.; Abee, H. H.; Gupton, E. D. & Warden, A. D.
System:
The UNT Digital Library
Gas-Cooled Reactor Project Semiannual Progress Report: September 1964
Report issued by the Oak Ridge National Laboratory discussing semiannual progress made by the Gas-Cooled Reactor Program. Descriptions of progress and studies conducted are presented. This report includes tables, illustrations, and photographs.
Date:
February 1965
Creator:
Trauger, D. B. & Whitman, G. D.
System:
The UNT Digital Library
Fuels and Materials Development Program Quarterly Progress Report, September 30, 1968
From Foreword: "Report containing information about ongoing research and development taking place in the Oak Ridge National Laboratory's Fuels and Materials Development Program. This includes a series of test reports covering such subjects as reactor fuels, the development of nitride fuels, and the effects of radiation on structural materials."
Date:
February 1969
Creator:
Oak Ridge National Laboratory. Metals and Ceramics Division.
System:
The UNT Digital Library
Health Physics Division Annual Progress Report, January 31, 1955
Report documenting research and developments made by the Health Physics Division of the Oak Ridge National Laboratory.
Date:
1956
Creator:
Oak Ridge National Laboratory. Health Physics Division.
System:
The UNT Digital Library
Health Physics Division Annual Progress Report, July 31, 1969
From summary: "Report documenting research and developments made by the Health Physics Division of the Oak Ridge National Laboratory."
Date:
October 1969
Creator:
Oak Ridge National Laboratory. Health Physics Division.
System:
The UNT Digital Library
Instrumentation and Controls Division Annual Progress Report, September 1, 1968
Report containing ongoing research and experiments of the Oak Ridge National Laboratory's Instrumentation and Controls Division.
Date:
February 1969
Creator:
Oak Ridge National Laboratory. Instrumentation and Controls Division.
System:
The UNT Digital Library
Molten-Salt Reactor Program Semiannual Progress Report for Period Ending August 31, 1968
From introduction: "Report containing ongoing projects and experiments undertaken by the Oak Ridge National Laboratory's Molten-Salt Reactor Program."
Date:
February 1969
Creator:
Oak Ridge National Laboratory
System:
The UNT Digital Library
Physics Division Semiannual Progress Report, September 10, 1955
Report containing papers, publications, and announcements from the Physics Division of the Oak Ridge National Laboratory.
Date:
1955~
Creator:
Oak Ridge National Laboratory. Physics Division.
System:
The UNT Digital Library
Solid State Division Semiannual Progress Report, August 30, 1955
Report containing papers, publications, and announcements from the Solid State Division of the Oak Ridge National Laboratory.
Date:
1955~
Creator:
Oak Ridge National Laboratory. Solid State Division.
System:
The UNT Digital Library
Physics Division Annual Progress Report, January 31, 1964
Report containing ongoing research and development of the Oak Ridge National Laboratory's Physics Division.
Date:
June 1964
Creator:
Oak Ridge National Laboratory. Physics Division.
System:
The UNT Digital Library
Mechanical Properties of Some Refractory Metals and their Alloys
Report regarding the mechanical properties of Niobium, Molybdenum, Tantalum, and Tungsten alloys. Includes a review of the scant literature regarding these elements.
Date:
April 1964
Creator:
McCoy, H. E., Jr.; Stephenson, R. L. & Weir, J. R., Jr.
System:
The UNT Digital Library
Corrosion of the Volatility Pilot Plant INOR-8 Hydrofluorinator and Nickel 201 Fluorinator During Forty Fuel-Pprocessing Runs with Zirconium-Uranium Alloy
Report documenting the corrosion of fluorinators of the Oak Ridge National Laboratory's volatility pilot plant. Includes descriptions of the fluorinators, their operating environments, and the results of their corrosion.
Date:
March 1965
Creator:
Youngblood, E. L.; Milford, R. P.; Nicol, R. G. & Ruch, J. B.
System:
The UNT Digital Library
Procedures for Fabricating Aluminum-Base ATR Fuel Elements
Report concerning the relatively inexpensive fabrication of an aluminum-based fuel element for the Oak Ridge National Laboratory's 250-Mw Advanced Test Reactor.
Date:
June 1964
Creator:
Beaver, R. J.; Patriarca, P. & Adamson, G. M.
System:
The UNT Digital Library
Oak Ridge National Laboratory Radioisotopes Procedures Manual
Manual for the Oak Ridge National Laboratory's Isotopes Development Center. Includes procedures for the production, storage, and shipment of radioisotopes.
Date:
June 1964
Creator:
Case, F. N.; Fuccillo, D. A., Jr.; Ewing, Sylvia B.; Acree, E. H.; McFarland, C. E.; Massey, B. J. et al.
System:
The UNT Digital Library
Laboratory Development of Processes for Fixation of High-Level Radioactive Waste in Glassy Solids. [Part] 3, Wastes from the Purex Solvent Extraction Process
Report concerning the fixation and disposal of toxic waste derived from the Purex solvent extraction process.
Date:
June 1965
Creator:
Clark, W. E.; Godbee, H. W. & Fitzgerald, C. L.
System:
The UNT Digital Library
Development of the Assembly Method for Fuel Elements for the Advanced Test Reactor
Report regarding the development of fuel elements for the Advanced Test Reactor. The designs for the side plates and joints are documented, as well as the assembly process of the fuel element.
Date:
1964
Creator:
Knight, R. W. & Leitten, C. F., Jr.
System:
The UNT Digital Library
A Computer Code (CDC 1604A or IBM 7090) for Calculating the Cost of Shipping Spent Reactor Fuels as a Function of Burnup, Specific Power, Cooling Time, Fuel Composition, and Other Variables
Report presenting the calculation of the costs incurred in shipping irradiated uranium-containing fuel elements. A computer code that designs a cask and calculates the shipping costs is presented. By use of the code, shipping costs were calculated for typical reactor fuels.
Date:
August 1964
Creator:
Salmon, Royes
System:
The UNT Digital Library