Serial/Series Title
Country
Decade
Month
7 Matching Results
Results open in a new window/tab. Unexpected Results? Search the Catalog Instead.
Results:
1 - 7 of
7
Quarterly Technical Progress Report, AEC Unclassified Programs: July-September 1965
Quarterly report describing progress on unclassified research programs funded by the U.S. Atomic Energy Commission during the first quarter of the 1966 fiscal year.
Date:
December 22, 1965
Creator:
North American Aviation. Atomics International Division.
System:
The UNT Digital Library
Operations Handbook for the North American Aviation, Inc. Research Reactor, Model L-3
Report describing reactor components, operational characteristics, and operating instructions for the Model L-3 research reactor.
Date:
December 11, 1953
Creator:
North American Aviation
System:
The UNT Digital Library
Remote Maintenance Techniques for the Processing Refabrication Experiment
Abstract: This report outlines the general techniques developed for replacement of PRE in-cell equipment or equipment components.
Date:
December 1, 1958
Creator:
Stoker, Donald J.
System:
The UNT Digital Library
Study of SCTI Control System
Introduction: This report has been prepared to document the extensive analytical work required to design the control system for the Sodium Components Test Installation (SCTI), constructed for the Atomic Energy Commission at the Atomics International field laboratory.
Date:
December 1, 1964
Creator:
Griffin, C. W.
System:
The UNT Digital Library
Piqua Nuclear Power Facility Operations Analysis Program Progress Report Number 4: January-June 1964
Progress report for the Piqua Reactor Operations Analysis Program describing observations and analyses at the Piqua Nuclear Power Facility (PNPF). The program goals are to monitor operations and collect data in order to ensure that the plant's operation is safe, to improve design and performance, to evaluate the performance and lifetime of the plant's components and systems, to evaluate plant safety and safeguards, and to disseminate all information to the scientific community.
Date:
December 15, 1964
Creator:
Cole, H. S.; Hausknecht, D. F.; Jenkins, O. G., Jr.; Lew, D. E.; Mandel, H.; Pearson, E. N. et al.
System:
The UNT Digital Library
Hazards Analysis of the Organic Moderated Reactor Experiment
Introduction: The description of the Organic Moderated Reactor Experiment, (OMRE), its location, its safety system, and operative procedures have been previously detailed. The present report, although dealing with the subject of OMRE safety, has the more detailed intent of (1) determining the behavior of the OMRE under extremely unlikely sets of conditions; and (2) providing additional design information in the areas of reactivity coefficients, burnout heat flux, and reactor control.
Date:
December 15, 1959
Creator:
Williams, R. O., Jr.; Allen, W. O.; Ash, E. B.; Scott, W. W.; Shimazaki, T. T.; Sletten, H. L. et al.
System:
The UNT Digital Library
Reactor Physics, Quarterly Progress Report, August-October, 1953
"A thorough analysis of the data obtained on depleted, natural, and enriched uranium lattices has been made. Consideration of the possible sources of discrepancies between theory and experiment has led to a suspicion of the calculated thermal neutron diffusion lengths. A series of diffusion length measurements in non-multiplying lattices of lead-cadmium alloy has been initiated. An analysis of some early exponential experiments on lattices proposed for a neutron production reactor has been carried out in order to determine whether experimental results on these more complicated structures are consistent with the analysis carried out for the "clean" lattices."
Date:
December 10, 1953
Creator:
Laubenstein, R. A.
System:
The UNT Digital Library