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Halogen Collector Test Program
Report documenting the Halogen Collector Test program, which was undertaken to provide "methods of removing trace quantities of radioactive iodine from an air stream" (p. 1). The report includes designs of the program and the test facility, test results, analysis of these results, and encountered problems. Appendices begin on page 38.
Date:
March 1, 1960
Creator:
Arthur D. Little, Inc.
System:
The UNT Digital Library
Enrico Fermi Atomic Power Plant
Report describing the Enrico Fermi Atomic Power Plant, its fast breeder reactor, and heat transport systems.
Date:
March 1960
Creator:
Atomic Power Development Associates
System:
The UNT Digital Library
Fast Reactor Core Design Parameter Study
Report describing parametric studies of eleven fast reactor fuel systems undertaken to determine the design and economic factors for producing electricity. The methods used for making the parametric studies are described, as well as the results of these studies. Appendices begin on page 103.
Date:
March 1960
Creator:
Atomic Power Development Associates
System:
The UNT Digital Library
Final Design Report: DR-1 Gas Loop
Report describing the performance, fission product tolerance, design, and costs of the DR-1 Gas Loop, which is an in-reactor test facility.
Date:
March 1961
Creator:
Baars, R. E.
System:
The UNT Digital Library
Heavy-Water-Moderated Power Reactors: a Status Report
From introduction: "Evaluation of the present economic and technological status of power reactors that are cooled and moderated by heavy water and fueled with natural uranium."
Date:
March 1960
Creator:
Babcock, Dale Friend
System:
The UNT Digital Library
Evaluation of Failed Hot Gas Isostatic Pressed Fuel Rods
From introduction: "Evaluations to determine cause of fuel rods breakage following irradiation."
Date:
March 20, 1963
Creator:
Baroch, C. J. & Boyer, C. B.
System:
The UNT Digital Library
SM-1 (APPR-1) Research and Development Program : Final Report on Short-Lived and Fission Product Activity in the SM-1 Primary Coolant, Task III
Abstract: The primary coolant of the SM-1 (APPR-1) was analyzed for short-lived and fission product activities. Manganese-56 was found to be the predominant non-fission product nuclide contributing to the short lived activity. Fission products were found in the coolant. It is concluded these fission products originate from a defects in the cladding and from surface contamination of the fuel elements.
Date:
March 10, 1959
Creator:
Brown, William S. & Hasse, Robert A.
System:
The UNT Digital Library
Hazards Summary Report for the SM-1 Core Temperature and Flow Instrumentation: Task XIV
Abstract; This technical report describes the changes in the SM-1 incurred by the experiment, Core Temperature and Flow Instrumentation (Task XIV), and evaluates the possible hazard involved in these changes. Temperature and flow measurements will be taken on a Task XIV instrumented stationary fuel element, instrumented control rod fuel element and other selected points in the SM-1 core to provide data on the core steady state and transient performance. The hazards evaluation consists of a nuclear evaluation, thermal and hydraulic analysis, description of tests to be performed, and discussion of containment integrity and maximum accident considerations.
Date:
March 30, 1961
Creator:
Coombe, J. R.; Brondel, J. O.; Lee, D. H. & Matthews, F. T.
System:
The UNT Digital Library
Hazards Report for the SM-1 Core II With Special Components
Abstract: This technical report describes the changes incurred in the SM-1 by the insertion of the SM-1 Core II and special components. The special components consist of impact specimens, a boron gradient rod, SM-2 elements, a PM-1-M element, and high burnup SM-1 Core I elements. The change in hazards, due to operation of SM-1 with Core II and the special components is evaluated. The analysis indicates there is no change in hazards.
Date:
March 30, 1961
Creator:
Coombe, J.; Lee, D.; Segalman, I. & Robertson, R.
System:
The UNT Digital Library
Subcritical and Critical Flow Through Straight-Through, Elbow, and Tee "AN" Fittings and Sharp-Edged Orifices at Elevated Temperatures
Investigation of the flow through straight-through , elbow, and tee "AN" fittings at negligible approach velocity with approach temperatures up to 1100 degrees F.
Date:
March 6, 1957
Creator:
Ducoffe, Arnold L.; Bennett, John R. & Ray, C. Gable
System:
The UNT Digital Library
Summary Report of Design Criteria for a Thermal Flux Liquid Metal Package Loop in the Advanced Test Reactor
From introduction: "Report summarizing all work completed during the preparation of design criteria for thermal flux loop."
Date:
March 1963
Creator:
Ebasco Services Incorporated
System:
The UNT Digital Library
Plutonium Spike Fuel Elements for the Plutonium Recycle Test Reactor: Part 1 - The Mark 1-G
Report describing "[t]he fabrication of of the first aluminum-plutonium spike enrichment fuel elements for the Plutonium Recycle Test Reactor (PRTR) at Hanford" Laboratory (p. 2).
Date:
March 1961
Creator:
Freshley, M. D.
System:
The UNT Digital Library
An Addendum to a Parametric Study of the Gas-Cooled Reactor Concept
From introduction: "This report provides background information regarding the study results presented in the first volume of this report and provides information resulting from the studies made on the gas cooled reactor concept."
Date:
March 1, 1958
Creator:
Hanford Works
System:
The UNT Digital Library
Gamma-Ray Spectrometry of Neutron-Deficient Isotopes: Annual Progress Report, March 1964
From abstract: "The objective of this program is to produce a set of pulse-height spectra representing the response of a standard gamma-ray scintillation spectrometer to radiations emitted in the decay of neutron-deficient nuclides."
Date:
March 27, 1964
Creator:
Heath, R. L. & Cline, J. E.
System:
The UNT Digital Library
Data Book: Physical Properties and Flow Characteristics of Air
Data book to used as an aid in calculations on physical properties and flow characteristics of air.
Date:
March 1960
Creator:
Hobbs, J. L. & Lapides, Melvin E.
System:
The UNT Digital Library
Fire Test of Wooden-Jacket Shield for Radioisotope Shipping Container
"This report covers fire tests conducted on an experimental design of a wooden-jacket shield for radioisotope shipping containers" (p. i).
Date:
March 23, 1964
Creator:
Horn, Leonard H.
System:
The UNT Digital Library
PL-3 Phase I Task 3 Research and Development Report
Abstract: This technical report summarizes the results of research and development tasks performed during Phase I of this contract and presents recommendations for future development work. Work is reported in the areas of plant assembly and relocation, housings and footings, waste heat dissipation, instrumentation, refueling systems, waste disposal, shielding, core nuclear thermal and hydraulic studies, gaseous waste processing (BWR), and critical experiments on a 5 x 5 array of Type 3 fuel elements.
Date:
March 12, 1962
Creator:
Humphries, G. E.
System:
The UNT Digital Library
Preliminary Technical Report SM-1 Core III with Type 3 Elements
Abstract: This preliminary technical report covers design of the SM Type 3 element, its use .in.. SM-1 Core III, and planned use in the Type 3 Core for PM-2A. The Type:3 element characteristics are compared with Type 1 (SM-1 Core I) element nuclear, metallurgical, thermal and hydraulic characteristics and fabrication. The effect of using the Type 3 element in SM-1 Core III and. its planned use in a Type 3 Core for PM-2A is discussed with regard to operation, shielding, reactor safety and all conceivable special problems.
Date:
March 30, 1962
Creator:
Inglima, J. N.; Beam, R. H.; Davidson, S. L. & Edgar, E. C.
System:
The UNT Digital Library
Factors Affecting Fluidization of Uranium Trioxide Powders
Study of factors, such as the average particle size and particle-size distribution, which affect the fluidization properties of uranium trioxide powders.
Date:
March 1, 1958
Creator:
Johnson, B. M.
System:
The UNT Digital Library
Oak Ridge Site Report 30,000 KiloWatt Prototype Partially Enriched Uranium Gas Cooled, Graphite Moderated Nuclear Power Plant
From introduction: "This report describes the selected site for a prototype nuclear plant, the reactor safety aspects for the site, the modified design of the plant, and estimate of the design and construction cost."
Date:
March 1959
Creator:
Kaiser Engineers
System:
The UNT Digital Library
Design and Economic Evaluation of Mobile Blankets for Fast Reactors
Report evaluating the design characteristics and limitations of mobile blankets for breeder reactors. This also includes economic considerations for each tested blanket. Appendices begin on page 40.
Date:
March 10, 1964
Creator:
Klickman, A. E.; Ball, G. L.; Edwards, J. J.; Jens, W. H.; Segal, B. M.; Amorosi, A. et al.
System:
The UNT Digital Library
The Cold Pressing of Sinterable UO₂
The intent of this work was to explore more fully the pressing of sinterable UO2 powders into cylindrical compacts in the hope that a more precise prediction of green density in terms of powder properties, pressure, and geometry could be evolved.
Date:
March 27, 1961
Creator:
Levey, R. P., Jr.
System:
The UNT Digital Library
Summary Report of Analysis of Physics Measurements Performed on SM-1 Core I
Abstract: This technical report contains a comprehensive analysis of the nuclear characteristics of the SM-1 Core I. Comparison of analytical and experimental results for neutron ages and core reactivities of a variety of cases investigated shows that the MUFT III with P-1 slowing down approximation gives the best results. At startup the core reactivity and rod bank worth under various operating conditions are investigated and compared to experiment. Core lifetime was calculated to be 16.8 MWYR compared to 16.4 MWYR experimental. The temperature coefficient has been calculated and compared to experiment as function of burnup. In Appendix A, flux distribution, temperature coefficient, effective delayed neutron fraction and core life are analyzed by Dr. R. L. Murray by one and two group modified theory series expansion calculations.
Date:
March 30, 1962
Creator:
Lois, L.; Paluszkiewicz, S.; Fried, B. E. & Beam, R. H.
System:
The UNT Digital Library
Automatic Mass Spectrometer for Isotopic Analysis of Lithium
Report discussing an improvement program on lithium mass spectrometers.
Date:
March 15, 1962
Creator:
McBryde, W. T. & Gammon, E. F.
System:
The UNT Digital Library