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A Versatile Spectrometer Magnet Power Supply
Early results from actual laboratory operation of a more versatile magnet supply.
Date:
April 15, 1963
Creator:
Groppe, W. A.
System:
The UNT Digital Library
Metallurgy Research Operation: Quarterly Progress Report, January - March 1965
Quarterly progress report on a project to test the radiation effects on metallurgy.
Date:
April 15, 1965
Creator:
Cadwell, J. J.; Bierlein, T. K.; Bement, A. L.; Dillon, R. L. & Wheeler, R. G.
System:
The UNT Digital Library
A Sequence for Predicting Waste Transport by Ground Water
From introduction: "This paper describes a sequence for analyzing the effects of ground water flow on waste transport in natural soils."
Date:
April 15, 1965
Creator:
Nelson, R. William
System:
The UNT Digital Library
SL-1 Annual Operating Report: February, 1960-January 3, [1961]
The Stationary Low Power Reactor No. 1 (SL-1) was a boiling water reactor demonstration plant for remote military bases. The plant had been operated by Combustion Engineering, Inc. from February, l959 until January 3, 1961 at which time a nuclear excursion rendered the plant inoperable, This report summarizes the of operations of maintenance, test, health and safety, and administrative activities for the year February, 1960 until the incident.
Date:
June 15, 1961
Creator:
unknown
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
Evaluation and Consolidation of Electrolytic Thorium
Abstract: "Sound, fabricable ingots of thorium were produced by triple are melting of electrolytic thorium. Consumable electrodes were fabricated by tack welding of cold-pressed and vacuum-sintered bars of the granular thorium electrodeposited from a molten-salt bath. The hydrogen content of the electrodeposited material was reduced from 80 to 4 ppm by vacuum sintering at 1250 C at pressures below 1 x 10-(-3) mm of mercury. Both sodium and chlorine content were reduced during melting; sodium from 250 to 25 ppm and chlorine from 1000 to 30 ppm. Oxygen and HCl acid-insoluble contents increased during sintering and melting. Oxygen content increased from 0.35 to 0.50 w/o and HCl acid-insoluble content from 0.8 to 4.0 w/o. A starlike includion revealed by metallographic examination of the as-cast thorium was identified as ThO2."
Date:
June 15, 1955
Creator:
Saller, Henry A.; Dickerson, Ronald F. & Foster, Ellis L.
System:
The UNT Digital Library
OMR Control-Safety Rod Component Development Tests
Abstract: A magnetic-jack control-safety rod is under development for the 45.5 thermal megawatt Organic Moderated Reactor. The rod is "unitized," i.e., the poison element, drive, position indicator, and shock absorber are contained in a compact assembly which is inserted in a regular fuel channel opening in the core. Tests to develop components capable of operating under these conditions are described and results are reported.
Date:
September 15, 1959
Creator:
Howell, J. D.
System:
The UNT Digital Library
Coolant Flow and Outlet Temperature: Computer-Monitors for the Hallam Nuclear Power Facility Plant Protective System
Abstract: The design and application of two computers for the HNPF protective system is discussed.
Date:
September 15, 1961
Creator:
Schlein, H.
System:
The UNT Digital Library
Power Flattening in Sodium Graphite Reactors by Spatial Variation of Moderator Properties
Abstract: In the present study, the variation of moderator composition was postulated to be effected by the inclusion of varying amounts of beryllium oxide in the graphite of an SGR.
Date:
December 15, 1959
Creator:
Connolly, T. J.
System:
The UNT Digital Library
Hot-Pressure Bonding of OMR Fuel Plates
Abstract: An alluminum-clad low-enrichment, uranium-alloy fuel element of flat plate configuration has been proposed for the Organic Moderated Reactor (OMR).
Date:
November 15, 1959
Creator:
Alm, G. V.; Binstock, M. H. & Garrett, E. E.
System:
The UNT Digital Library
Organic Reactor Waste Gas Analyzer
The design of a waste-gas treatment system for organic moderated reactors requires a knowledge of reactor waste-gas composition, generation rate, and radioactivity. To obtain data on these variables a continuous stream analyzer was constructed to analyze the waste gas from the Organic Moderated Reactor Experiment (OMRE).
Date:
October 15, 1958
Creator:
Gilroy, H. M. & Edwards, R. J.
System:
The UNT Digital Library
Terminal Status Report for the Processing Refabrication Experiment
Introduction: A low-capacity, low-decontamination plant can be built, as part of a power reactor complex, to avoid long distance transfer of fuel to a high-capacity aqueous processing plant. Activation of such a complex, with the processing plant adjacent to the reactor it serves, could decrease the cost of the integrated fuel cycle. The study of this concept is a major objective of the Processing Refabrication Experiment (PRE).
Date:
November 15, 1959
Creator:
Sinizer, D. I.; Mattern, K. L. & Kendall, E. G.
System:
The UNT Digital Library
Analysis of Stresses in Bellows
Abstract: Design charts and systematic design forms are presented for simplified calculations to check the number of convolutions and thickness required to limit the deflection and pressure stress range in three types of bellows.
Date:
October 15, 1964
Creator:
Anderson, W. F.
System:
The UNT Digital Library
An Advanced Sodium-Graphite Reactor Nuclear Power Plant
Abstract: This report describes an advanced sodium-cooled, graphite-moderated nuclear power plant which utilizes high-pressure, high-temperature steam to generate electricity at a high thermal efficiency.
Date:
March 15, 1960
Creator:
Churchill, J. R. & Renard, J.
System:
The UNT Digital Library
A Multichannel Digital Recording System
Abstract: This report is a description of a 200 channel digital recording system used to record high temperature strain gage outputs and associated temperatures.
Date:
September 15, 1960
Creator:
Truitt, R. W.
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
Thermal Cycling Tests of Porous Uranium
Abstract: It has been proposed that a fuel element containing porous uranium be used for moderately high temperature applications. In an effort to determine the structural integrity of this type of fuel body, thermal cycling tests have been conducted on porous uranium.
Date:
March 15, 1960
Creator:
Wilkinson, L. E.
System:
The UNT Digital Library
Fabrication Modification Development for OMRE Third Core Loading
Abstract: This report describes the fabrication of elements for the OMRE third core loading.
Date:
July 15, 1961
Creator:
Peters, E. & Binstock, M. H.
System:
The UNT Digital Library
Design Modifications to the SRE during FY 1960
Abstract: The means to prevent the recurrence of tetralin leakage into the SRE sodium systems are discussed. Included is a description of the redesign of system components to utilize alternate coolants such as nitrogen, air, and NaK.
Date:
February 15, 1961
Creator:
Deegan, G. E.; Dermer, M. D.; Flanagan, J. S.; Gower, G. C.; Hall, R. J.; Hinze, R. B. et al.
System:
The UNT Digital Library
Metallurgical Aspects of SRE Fuel Element Damage Episode
Abstract: An investigation of the metallurgical aspects of the SRE fuel element episode, that occurred July 26, 1959, has been completed.
Date:
October 15, 1961
Creator:
Ballif, J. L.
System:
The UNT Digital Library
Investigations of Neutron Penetration in TiH and Steel Slabs
Abstract: A multigroup P1 approximation for hydrogen scattered neutrons has been developed and applied to the study of neutron flux distributions in titanium hydride and steel shield systems.
Date:
May 15, 1961
Creator:
Karcher, R. H.
System:
The UNT Digital Library
Criticality-Accident Dosimetry Studies
Experiments were carried out to (1) explore possibilities for developing a less expensive device than the Hurst threshold detector unit (TDU) for monitoring possible accidental critical reactions in uranium-processing facilities, (2) to study the precision and accuracy of the TDU, and (3) to evaluate the ORNL film badge in mixed neutron-gama radiation fields.
Date:
October 15, 1964
Creator:
Bailey, J. C.
System:
The UNT Digital Library
Operating Experience with Heat Transfer System Pumps at the Hallum Nuclear Power Facility
Introduction: It is the purpose of this report to describe the operating and maintenance experience obtained at HNPF on the sodium heat transfer pumps.
Date:
June 15, 1964
Creator:
Durand, R. E.
System:
The UNT Digital Library
SNAP 10A FSEM-3 Agena Compatibility Test
From abstract: This report summarizes the results of SNAP-10A/Agena developmental testing and final vehicle systems tests.
Date:
June 15, 1965
Creator:
Teresa, M.
System:
The UNT Digital Library