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Steam Cycle Optimization Study for Large Sodium Graphite Nuclear Power Generating Stations
Abstract: This report presents steam cycle optimization studies for large sodium graphite nuclear power generating stations.
Date:
August 31, 1964
Creator:
Schneider, G. A.
System:
The UNT Digital Library
UC Fuel Element Design and Fabrication
Abstract: Uranium monocarbide shows considerable potential for use as a fuel in high temperature, high power density, nuclear power reactors. As Atomics International is proposing its use in sodium graphite type reactors, it was necessary to develop a process for fabricaing sodium bonded uranium carbide fuel elements.
Date:
August 1, 1964
Creator:
Draganchuk, W.
System:
The UNT Digital Library
Boiling Depressurization Transients
Abstract: An analytical and experimental effort toward a better understanding of the mechanisms involved in nuclear power reactor loss-of-pressure accidents is presented.
Date:
August 1, 1964
Creator:
Halfen, F. J. & Berganzoli, F.
System:
The UNT Digital Library
Uranium Carbide Transient Heating Experiments - Phase 1
Abstract: Two in-pile capsules containing mock-up uranium carbide fuel rods were subjected to a total of five neutron bursts in the TREAT facility with initial reactor periods ranging from 0.26 to 0.10 sec.
Date:
August 1, 1964
Creator:
Stachura, S. J.; Silberberg, M. & Cordy, R. N.
System:
The UNT Digital Library
The Continuous Neutron Flux Monitor Project: An Interim Report
Abstract: A new concept for continuously monitoring neutron flux has been successfully tested.
Date:
August 1, 1964
Creator:
Smith, Charles R. F. & Springer, Thomas H.
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
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
Progress in Nondestructive Testing: A Summary of Hanford Achievements in These Programs Under General Electric, 1952 - 1964
Report discussing the development of Hanford Laboratories' nondestructive testing programs and a summary of their results. Programs include AlSi fuel testing, N-Reactor fuel testing, and reactor research and development.
Date:
August 1964
Creator:
Walker, R. A. & Russell, J. T.
System:
The UNT Digital Library
Scintillation Spectrometry Gamma-Ray Catalogue: Volume 2
Gamma-Ray Spectrum diagrams.
Date:
August 1964
Creator:
Heath, R. L.
System:
The UNT Digital Library
The High Flux Isotope Reactor: Volume 2, Selected Construction Drawings
Report containing a series of drawings detailing the Oak Ridge National Laboratory's high flux isotope reactor, its surroundings, and its systems.
Date:
August 1964
Creator:
Binford, F. T.; Cramer, E. N. & Cramer, E. N.
System:
The UNT Digital Library