Country
States
Comparative Cost Study of Processing Stainless Steel-Jacketed UO2 Fuel: Mechanical Shear-Leach vs Sulfex-Core Dissolution
Comparison of the economics of mechanical shear-leach and Sulfex decladding-core dissolution head end treatments for processing typical tubular bundles of stainless steel-jacketed UO2 nuclear fuels.
Date:
April 23, 1962
Creator:
Adams, J. B.; Benis, A. M. & Watson, C. D.
System:
The UNT Digital Library
Chemical Technology Division Annual Progress Report: for Period Ending June 30, 1962
Report issued by Oak Ridge National Laboratory that discusses progress and work performed by the Chemical Technology Division.
Date:
September 21, 1962
Creator:
Oak Ridge National Laboratory. Chemical Technology Division.
System:
The UNT Digital Library
Gas-Cooled Reactor Project Semiannual Progress Report: September 1962
Report documenting the design and testing progress of the Oak Ridge National Laboratory's Gas-Cooled Reactor Program.
Date:
1962
Creator:
Oak Ridge National Laboratory
System:
The UNT Digital Library
Health Physics Division Annual Progress Report, July 31, 1962
Report documenting research and developments made by the Health Physics Division of the Oak Ridge National Laboratory.
Date:
1962
Creator:
Oak Ridge National Laboratory. Health Physics Division.
System:
The UNT Digital Library
Oak Ridge Metals and Ceramics Division Annual Progress Report: 1962
Report documenting research and developments made by the Metals and Ceramic Division of the Oak Ridge National Laboratory.
Date:
1962~
Creator:
Oak Ridge National Laboratory. Metals and Ceramics Division.
System:
The UNT Digital Library
Facility For Photographing in-Pile Meltdown Experiments in TREAT
Report regarding the fabrication of a transparent meltdown facility for the purpose of photographing simulated meltdowns.
Date:
January 1962
Creator:
Golden, G. H.; Dickerman, C. E. & Robinson, L. E.
System:
The UNT Digital Library
The Facility 350 Helium-Atmosphere System
Report describing the helium atmosphere system in the Argonne National Laboratory's Facility 350. The atmosphere's ability to remove moisture, oxygen, and other impurities, how the atmosphere is purified, and experimental data regarding the use of activated carbon to absorb oxygen from helium are discussed.
Date:
December 1962
Creator:
Mayfield, R. M.; Tope, W. G. & Shuck, A. B.
System:
The UNT Digital Library
Experimental Breeder Reactor-II (EBR-II) Shield Design
Report describing the EBR-II shield and the methods employed in arriving at the final design. The major shield design problems for that reactor are enumerated and discussed.
Date:
September 1962
Creator:
Grotenhuis, M.; McArthy, A. E. & Rossin, A. D.
System:
The UNT Digital Library
Molten-Salt Reactor Program Semiannual Progress Report, February 28, 1962
Report issued by the Oak Ridge National Laboratory discussing semiannual progress made by the Molten-Salt Reactor Program. Descriptions of design, construction, and experimental progress are presented. This report includes tables, illustrations, and photographs.
Date:
1962
Creator:
Oak Ridge National Laboratory
System:
The UNT Digital Library
Reactor Chemistry Division Annual Progress Report for Period Ending January 31, 1962
Report containing the ongoing research and developments of the Oak Ridge National Laboratory's Reactor Chemistry Division.
Date:
1962
Creator:
Oak Ridge National Laboratory
System:
The UNT Digital Library
In-Pile Loop Irradiation of Aqueous Thoria-Urania Slurry at Elevated Temperature : Design and In-Pile Operation of Loop L-2-27S
Report describing the design and operation of Loop L-2-275, which was used in the irradiation an aqueous thoria-urania slurry.
Date:
1962
Creator:
Savage, H. C.; Compere, E. L.; Baker, J. M.; DeCarlo, V. A. & Shor, A. J.
System:
The UNT Digital Library
Health Physics Research Reactor Hazards Summary
Report describing the design and operation of the Health Physics Research Reactor, its core, and its support structures.
Date:
1962
Creator:
Lundin, M. I.
System:
The UNT Digital Library
Oak Ridge Analytical Chemistry Division Annual Progress Report: 1962
Report issued by the Oak Ridge National Laboratory discussing progress and work conducted by the Chemistry Division.
Date:
December 11, 1962
Creator:
Oak Ridge National Laboratory. Chemistry Division.
System:
The UNT Digital Library
Gas-Cooled Reactor Project Quarterly Progress Report: December 1961
Report documenting ongoing research and developments at the Oak Ridge National Laboratory's Gas-Cooled Reactor Project.
Date:
April 6, 1962
Creator:
Oak Ridge National Laboratory
System:
The UNT Digital Library
Gas-Cooled Reactor Project Quarterly Progress Report: March 1962
Report documenting the ongoing research and developments at the Oak Ridge National Laboratory's Gas-Cooled Reactor Program.
Date:
1962
Creator:
Oak Ridge National Laboratory
System:
The UNT Digital Library
Maritime Reactor Project Annual Progress Report, November 30, 1961
Report issued by the Oak Ridge National Laboratory discussing annual progress made by the Maritime Reactor Program. Progress and studies conducted during 1961 are presented. This report includes tables, illustrations, and photographs.
Date:
1962~
Creator:
Oak Ridge National Laboratory
System:
The UNT Digital Library
Plutonium Recycle Test Reactor Final Safeguard Analysis: Supplement 4, Gas-Cooled Loop Anaysis
Plutonium Recycle Test Reactor (PRTR) final safeguards analysis involving a gas-cooled loop.
Date:
March 1962
Creator:
Wittenbrock, N. G.
System:
The UNT Digital Library
Evaluation of Properties of Irradiated Zircaloy-2 Pressure Tube from KER Loop 1
Report describing the evaluation of the effects of irradiation on a high pressure water loop that ruptured while testing fuel elements. Includes photographs of the damaged tube as well as chemical analyses.
Date:
December 1962
Creator:
Defferdin, L. J.
System:
The UNT Digital Library
Plutonium Recycle Critical Facility: Final Safeguards Analysis
Report discussing the Plutonium Recycle Critical Facility (PRCF). The reactor, building, associated equipment, operating program, safety, and operating procedures are described.
Date:
February 1962
Creator:
Anderson, J. K. & Winegardner, W. K.
System:
The UNT Digital Library
Thermal Conductivity of UO2
Report discussing the thermal conductivity of uranium dioxide. The first part of the report includes the thermal effects on the substance's physical form, while the second part describes the experimental details.
Date:
September 1962
Creator:
Daniel, J. L.; Matolich, J., Jr. & Deem, H. W.
System:
The UNT Digital Library
Research and Development Activities in the Radiological Sciences, Physical Sciences Portion, January - December 1961
Report regarding ongoing research and development undertaken at Hanfdord Laboratories' physics and instruments laboratory and chemical laboratory.
Date:
January 15, 1962
Creator:
Junkins, R. L. & Brown, J. E.
System:
The UNT Digital Library
Magnetic Force Welding Sintered Aluminum Powder Materials
Report discussing the use of sintered aluminum powder for nuclear fuel cladding. This report includes descriptions of pertinent materials and experimental procedures.
Date:
March 1962
Creator:
Mills, L. E.
System:
The UNT Digital Library
Strength and Metallurgical Properties of the Zircaloy-2 Pressure Tubes for the Plutonium Recycle Test Reactor
Report describing the properties of the Zircaloy pressure tubes at the Plutonium Recycle Test Reactor. Topics include the fabrication of these tubes, their mechanical properties, and operating stresses.
Date:
March 1962
Creator:
Knecht, R. L. & Pankaskie, P. J.
System:
The UNT Digital Library
Calculated Costs of Fabrication of Plutonium-Enriched Fuel Elements
Report regarding the study of the calculated costs of fabricating plutonium-enriched fuel elements for Hanford Laboratories' Plutonium Recycle Program. Topics include descriptions of the process, design study of plants that use U235 and plutonium enriched fuel, and estimates of costs.
Date:
August 1962
Creator:
Hanthorn, H. E.
System:
The UNT Digital Library