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108 Matching Results
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Thermal Stress Testing of Beryllium Oxide Moderator Shapes
Abstract: Perforated BeO plates were thermal shock tested to evaluate the effect of: (1) localized temperature variations adjacent to the perforations, and (2) radial gradients across the entire plate.
Date:
August 1, 1962
Creator:
Sujata, H. L.; King, M. & Waters, F. J.
System:
The UNT Digital Library
Piqua Nuclear Power Facility Operations Analysis Program Progress Report Number 5: July-December 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:
June 15, 1965
Creator:
unknown
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
Piqua Nuclear Power Facility Operations Analysis Program Progress Report Number 9: 1966
The following progress report describes the examination of elements removed in comparison to a previous study on the power facility reactor operations.
Date:
May 1969
Creator:
North American Aviation. Atomics International Division.
System:
The UNT Digital Library
Piqua Nuclear Power Facility Operations Analysis Program Progress Report Number 8: 1966
The following progress report describes the examination of elements removed in comparison to a previous study on the power facility reactor operations.
Date:
December 31, 1966
Creator:
North American Aviation. Atomics International Division.
System:
The UNT Digital Library
Irradiation behavior of unalloyed hypostoichiometric uranium carbide, experiment AI 3-11 and review
A report regarding the irradiation behavior of Unalloyed hypostoichiometric uranium carbide experiment AI 3-11 and review
Date:
June 22, 1968
Creator:
Frank, J. E.; Forrester, R. E. & Buck, J. S.
System:
The UNT Digital Library
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
Stress and Elevated Temperature Fatigue Characteristics of Large Bellows
From abstract: Charts in this report show axial stress distribution over exterior bellows surfaces induced by bellows axial deflection, and by internal pressurization. The influence of root rings on stress distribution is presented graphically.
Date:
September 15, 1964
Creator:
Winborne, R. A.
System:
The UNT Digital Library
Steady-State Tests of a Reactor Safety Device
Introduction: This is the fourth report in a series of reports dealing in particular with a reactor safety device of a double diaphragm type.
Date:
December 15, 1960
Creator:
Springer, T. H.
System:
The UNT Digital Library
A Device for Continuous Detection of Hydrogen in Sodium
Abstract: A device to detect the presence of hydrogen in sodium has been developed. Such a device, installed in a sodium heated steam generator, would signal the presence of water in the sodium resulting from a leak in the sodium-water barrier.
Date:
December 15, 1960
Creator:
Strahl, H.
System:
The UNT Digital Library
Analog Models for HNPF Control and Protection Studies
Abstract: This report, intended as a working document, contains analytic representations and analog models of the Hallam Nuclear Power Facility as used in studies of the Control and Protection Systems.
Date:
June 15, 1964
Creator:
Dunsmore, C. L.
System:
The UNT Digital Library
The FAIM Code: a Multigroup, One-Dimensional Diffusion Equation Code
Abstract: FAIM is a general multigroup, one-dimensional diffusion equation code programmed in FORTRAN language for the IBM 7090 computer.
Date:
April 15, 1962
Creator:
Baller, D. C.
System:
The UNT Digital Library
Critical Experiments on Slightly Enriched Uranium Metal Fuel Elements in Graphite Lattices
Abstract: A series of clean critical experiments was performed in the SGR critical facility utilizing 2 wt % enriched, uranium metal, hollow cylinder, fuel elements, in AGOT graphite moderator.
Date:
June 30, 1963
Creator:
Campbell, R. W.; Doyas, R. J.; Field, H. C.; Guderjahn, C. A.; Guenther, R. L.; Hausknecht, D. F. et al.
System:
The UNT Digital Library
Design of an Experimental Bowable Fuel Element for the SRE
Abstract: An experimental bowable fuel element was developed to study temperature oscillations in the second core loading of the SRE.
Date:
October 15, 1964
Creator:
Peckinpaugh, C. L.
System:
The UNT Digital Library
Inpile Experiments on Retention of Fission Products in 500°F Sodium
Abstract: The results of three separate inpile capsule experiments are presented.
Date:
January 30, 1964
Creator:
Kunkel, W. P.; Elliot, D. M. & Gibson, A. S.
System:
The UNT Digital Library
Increasing Thermocouple Reliability for in-Pile Experiments
Abstract: The results indicated that increased reliability can be obtained by using thermocouples made with insulation of increased density and/or a low thermal expansion sheath.
Date:
April 20, 1965
Creator:
Babbe, E. L.
System:
The UNT Digital Library
QUICKIE: A Computer Program for Spatially Independent Multigroup Slowing-Down and Thermalization Calculations
Introduction: QUICKIE is a computer program designed to solve the multigroup neutron slowing down and thermalization equations without consideration of spatial dimensions.
Date:
April 15, 1964
Creator:
Boling, M. & Rhoades, W.
System:
The UNT Digital Library
Hallam Nuclear Power Facility, Reactor Operations Analysis Program: Semiannual Progress Report Number 3, September 1963-February 1964
From introduction: This report provides industry, plant operators, and the scientific community with information covering the results of the performance analysis.
Date:
September 15, 1964
Creator:
Darley, D. K.
System:
The UNT Digital Library
Capsule Irradiation of Unalloyed Uranium at High Temperatures
Abstract: Cast and Wrought specimens and restrained wrought specimens of unalloyed uranium were irradiated in the Materials Testing Reactor, as the first in a series of experiments to develop fuel materials for sodium cooled reactors.
Date:
August 15, 1962
Creator:
Harrington, D. G. & Newton, J. B.
System:
The UNT Digital Library
Flux Control for Irradiation Experiments
Abstract: This report reviews various means which have been used to control experimental conditions in irradiation experiments, and presents the concept of local flux control.
Date:
February 1, 1965
Creator:
McCarty, W. K.
System:
The UNT Digital Library
SNAP 2: Structural and Dynamic Analysis
Abstract: The structural design criteria and the system basic loads for the SNAP 2 compact power unit are presented.
Date:
May 1, 1964
Creator:
Castle, R. A.
System:
The UNT Digital Library
Boiling Studies for Sodium Reactor Safety: Part 1, Experimental Apparatus and Results of Initial Tests and Analysis
Abstract: An experimental and analytical research program is described which is designed to meet certain specific needs for data and methods required to make improved predictions of transient voids, burnout, flow, and fuel temperature during extreme accidents in sodium-cooled reactors.
Date:
August 30, 1963
Creator:
Noyes, R. C.
System:
The UNT Digital Library
Application of Nuclear Power Plants (SNAP Units) to the Manned Orbiting Research Laboratory (MORL)
Abstract: This report describes in detail two designs of a nominal 6-kwe Nuclear Power Plant (NPP), one using thermoelectrics for power conversion and the other using the Mercury-Rankine cycle NPP.
Date:
February 1, 1965
Creator:
Botts, W. V.; Marko, M.; McCourt, P. E.; Keshishian, V.; Piccot, A. R. & Budney, G. S.
System:
The UNT Digital Library
Equilibrium Dissociation Pressures of the Delta and Epsilon Phases in the Zirconium-Hydrogen System
Abstract: Pressure-temperature isochores were obtained for zirconium-hydrogen alloys, spanning the H/Zr composition range of 1.430 to 1.910. The studies were confined to the temperature limits of 300 to 900ºC, and the pressure limits of 0.01 to 10.0 atm.
Date:
May 31, 1964
Creator:
Raymond, J. W.
System:
The UNT Digital Library