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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
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
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
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
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
Molten-Salt Reactor Program Semiannual Progress Report, March 1 - August 31, 1961
Report containing ongoing projects and experiments undertaken by the Oak Ridge National Laboratory's Molten-Salt Reactor Program.
Date:
1962
Creator:
Oak Ridge National Laboratory
System:
The UNT Digital Library
MUFT Revision : A Fast Neutron Spectrum Code for the IBM-650
Report documenting the MUFT-R program, which is "designed to solve the fast neutron transport problem for general mixtures of elements and obtain sets of average fast neutron diffusion constants for specified portions of the fast energy spectrum" (p. iii). Includes detailed derivations of utilized equations.
Date:
1962
Creator:
Grimesey, Robert A.; Mullen, Frank Edward & Gannon, L. J.
System:
The UNT Digital Library
Nuclear Superheat Quarterly Project Report: Fourth Quarter, April-June 1960
From introduction: "This is the fourth of a series of quarterly reports which will cover the progress and results from the conceptual design, economic evaluations and research and development work performed by the General Electric Company as part of the Nuclear Superheat Project."
Date:
January 1962
Creator:
U.S. Atomic Energy Commission
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 Analytical Chemistry Division. Instrumentation, analytical methods, reactor projects, service analysis, and special research is presented. This report includes tables, illustrations, and photographs.
Date:
1962~
Creator:
Oak Ridge National Laboratory. Analytical Chemistry 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
Pulse Amplifier Manual
Manual for the use and repair of repair pulse amplifiers. This covers general testing routines, specific tests, and a bibliography of related materials.
Date:
1962
Creator:
Fairstein, E.
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
Critical Path Scheduling of ETR and MTR Reactor Shutdowns
Report describing a method for planning shutdown projects and scheduling the manpower to shut down Materials Testing Reactors (MTR) and Engineering Test Reactors (ETR).
Date:
January 10, 1962
Creator:
Jacobs, R. T. & Myers, L. L.
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
Investigation of 17-4 PH Steel Components Used in SM-1, SM-1A, PM-2A Reactor Plants
Abstract: This technical report covers the investigation of 17-4 PH steel components used in the SM-1, SM-1A and PM-2A nuclear power plants, which consist of control rod drive racks, pinions, seal shafts and associated parts. Evidence supporting the continued use of 17-4 PH steel in these applications is presented. Alco's current procurement and processing specifications for 17-4 PH steel are included. The evidence presented is in the form of stress calculations, test and environmental data and the results of non-destructive and destructive metallographic analyses.
Date:
January 23, 1962
Creator:
Haraway, E. S. & Saccocio, R. M.
System:
The UNT Digital Library
Special Power Excursion Reactor Test III Pressurizer Vessel Failure
Report documenting results of a study of the cause of failure at the SPERT III reactor facility.
Date:
January 29, 1962
Creator:
Heffner, R. E.; Wilson, T. R.; Halls, D. P.; Hickman, W. W. & Hoopingarner, K. R.
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
Salt Bath Heat Transfer Rates for Uranium Plate
Experiment to study temperature conditions during a five-minute heating cycle in the annealing of uranium sheets used as fissile material.
Date:
February 1, 1962
Creator:
Burditt, R. B.
System:
The UNT Digital Library
Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 2. Plant Conceptual Studies
Second part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. II-i).
Date:
March 1962
Creator:
Combustion Engineering, inc. Nuclear Division.
System:
The UNT Digital Library
Evaluation of Zirconium Hydride as Moderator in Integral, Boiling Water-Superheat Reactors
This report summarizes the results and conclusions of a study made to evaluate the merits of using zirconium hydride as a solid moderator in an integral boiling water-nuclear superheat reactor of the pressure vessel type.
Date:
March 1, 1962
Creator:
Gylfe, J. D.; Rood, H.; Greenleaf, J.; Balkwill, K.; Prem, L. & Goldfisher, L.
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
Multi-Channel Boiling Stability for Sodium Graphite Reactors
Abstract: This report presents an analysis of coolant boiling in sodium graphite reactors.
Date:
March 1, 1962
Creator:
Cappel, H. H.
System:
The UNT Digital Library
Nuclear Superheat Quarterly Project Report: Eighth Quarter, April-June 1961
From introduction: "This is the eighth of a series of quarterly reports which will cover the progress and results from the conceptual design, economic evaluations and research and development work performed by the General Electric Company as part of the Nuclear Superheat Project."
Date:
March 1962
Creator:
Pennington, R. T.
System:
The UNT Digital Library