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Nuclear Safety Program Annual Progress Report for Period Ending December 31, 1967
Annual progress report of safety program for several laboratory divisions.
Date:
April 1968
Creator:
unknown
System:
The UNT Digital Library
An Elliptic Integral Computer Package for Magnetic Fields, Forces, and Mutual Inductances of Axisymmetric Systems, and a Versatile Line-Tracing Routine
Report describing a set of high-precision routines for the IBM 7090 that perform efficiently the calculations most often required on axially symmetric magnetic systems. The routines compute the vector potential, field components, and the mixed gradient for current systems and for certain idealized distributions of magnetized matter. The programs for the current systems were developed from a set of six equations in elliptic integrals, which suffice when correlations are fully exploited for all the relevant properties of loops and solenoids.
Date:
April 1965
Creator:
Garrett, M. W.
System:
The UNT Digital Library
Measurement of α, the Ratio of the Neutron Capture Cross Section to the Fission Cross Section, for ²³⁵U in the Energy Region from 3.25 eV to 1.8 keV
Report issued by the Oak Ridge National Laboratory discussing techniques to obtain measurements of alpha for enriched uranium. Descriptions of equipment and experiments used to obtain alpha are presented. This report includes tables, and illustrations.
Date:
April 1965
Creator:
deSaussure, G.; Weston, L. W.; Gwin, R.; Russell, J. E. & Hockenbury, R. W.
System:
The UNT Digital Library
Optical Mapping of Oak Ridge Research Reactor Experiment Tubes
Report issued by the Oak Ridge National Laboratory discussing optical mapping of experiment tubes. Descriptions of experiment equipment, and designs of the tubes are presented. This report includes tables, illustrations, and photographs.
Date:
April 1965
Creator:
Abbatiello, A. A.
System:
The UNT Digital Library
Spectra of Gamma Rays Produced by the INteraction of ~160-MeV Protons with Be, C, O, Al, Co, and Bi
Report concerning the production of gamma ray spectra of gamma rays by the interaction of ~160-MeV protons with beryllium, carbon, oxygen, Aluminum, carbon monoxide, and bismuth. This also includes descriptions of the apparatus used and a discussion of the results.
Date:
April 1965
Creator:
Zobel, W.; Maienschein, F. C. & Scroggs, R. J.
System:
The UNT Digital Library
An Assessment of Certain Avenues of Improvement for Nuclear Desalination Technology
From the questions which have been asked, I gather that I am expected to bring you the news of the latest exciting developments in desalination at the Oak Ridge National Laboratory. However, the agenda for this meeting does not include reports of unfinished investigations; moreover, although there are some new ideas afoot at Oak Ridge, they are aimed toward the very large stations which are somewhat beyond the scope of the more current interests represented here. So instead of presenting new developments, I would like today to talk about where to look for them--to give you some purely analytical considerations that assess the incentives we have to seed certain improvements in this or that portion of the equipment in a dual-purpose station.
Date:
April 1964
Creator:
Hammond, R. Philip
System:
The UNT Digital Library
Mechanical Properties of Some Refractory Metals and their Alloys
Report regarding the mechanical properties of Niobium, Molybdenum, Tantalum, and Tungsten alloys. Includes a review of the scant literature regarding these elements.
Date:
April 1964
Creator:
McCoy, H. E., Jr.; Stephenson, R. L. & Weir, J. R., Jr.
System:
The UNT Digital Library
Recent Studies of Boiling Burnout
Five recent investigations of the critical heat flux in water systems are described. These studies were conducted in the interval from early 1963 through the present. The five studies are (1) Pool studies: inherent uncertainty in the critical heat flux; (2) Pool studies: heat transfer inside of horizontal, open ended heated tubes immersed in a pool; (3) Pool studies: natural-convection burnout of closed vertical channels; (4) Forced-convection investigations; subcooled boiling and burnout with heated twisted tapes; and (5) Forced-convection investigations; swirl-flow forced-convection bulk-boiling loop.
Date:
April 1964
Creator:
Gambill, W. R.
System:
The UNT Digital Library
Some Major Fuel-Irradiation Test Facilities of the Oak Ridge National Laboratory
Report describing various reactors, six thermal conduction capsules, three loop facilities, miscellaneous equipment, and shop facilities maintained by the Oak Ridge National Laboratory.
Date:
April 1964
Creator:
Trauger, Donald B.
System:
The UNT Digital Library
Thorium-Uranium-233 Oxide (Kilorod) Facility : Rod Fabrication Process and Equipment
Report documenting "the design, construction, and operation of the Kilorod Facility and its fabrication equipment" (p. 42) as well as its economic viability.
Date:
April 1964
Creator:
Sease, J. D.; Lotts, A. L. & Davis, F. C.
System:
The UNT Digital Library
Army Reactors Program Annual Progress Report: 1962
Report summarizing ongoing nuclear work performed by the ORNL for the United States Army.
Date:
April 10, 1963
Creator:
Oak Ridge National Laboratory
System:
The UNT Digital Library
Fuel Cycle Program Progress Report: Eleventh Quarter, January-March 1963
Quarterly progress report discussing activities related to the Vallecitos Boiling Water Reactor (VBWR) and related facilities.
Date:
April 5, 1963
Creator:
Howard, C. L.
System:
The UNT Digital Library
Maritime Reactor Project Annual Progress Report: for Period Ending November 30, 1962
Report documenting research and developments made by the Maritime Reactor Program of the Oak Ridge National Laboratory.
Date:
April 4, 1963
Creator:
Oak Ridge National Laboratory
System:
The UNT Digital Library
Cumulative Bibliography of Literature Examine by the Radiation Shielding Information Center
This bibliography represents the first cumulative edit of the literature examined by the Radiation Shielding Information Center recently established at the Oak Ridge National Laboratory. Its two major sections consist of a list of documents by subject category and of an author index. The document list covers nine major subjects with a total of 118 categories; however, literature specimens have not yet been entered for all categories. If a document applies to more than one category, it is listed under each. The author index includes cross references to the categories under which each author's publications appear. Preceding the bibliography is a list of the subject categories, their corresponding category numbers and the pages on which they appear in the bibliography,
Date:
April 1963
Creator:
Radiation Shielding Information Center (U.S.)
System:
The UNT Digital Library
Sodium-Cooled Reactors Program, Fast Ceramic Reactor Development Program: Sixth Quarterly Report, January-March 1963
Quarterly report discussing progress on the Fast Ceramic Reactor Development Program, "an integrated analytical and experimental program directed toward the development of fast reactors employing ceramic fuels, with particular attention to mixed plutonium-uranium oxide" (p. 1).
Date:
April 1963
Creator:
Leitz, F. J.
System:
The UNT Digital Library
Comparative Cost Study of Processing Stainless Steel-Jacketed UO2 Fuel: Mechanical Shear-Leach vs Sulfex-Core Dissolution
Comparison of the economics of mechanical shear-leach and Sulfex decladding-core dissolution head end treatments for processing typical tubular bundles of stainless steel-jacketed UO2 nuclear fuels.
Date:
April 23, 1962
Creator:
Adams, J. B.; Benis, A. M. & Watson, C. D.
System:
The UNT Digital Library
Gas-Cooled Reactor Project Quarterly Progress Report: December 1961
Report documenting ongoing research and developments at the Oak Ridge National Laboratory's Gas-Cooled Reactor Project.
Date:
April 6, 1962
Creator:
Oak Ridge National Laboratory
System:
The UNT Digital Library
Polfit II, an IBM 7090 Program for Polynomial Least Squares Fitting
Program written to perform polynomial least squares fits on the the IBM 7090 computer.
Date:
April 24, 1961
Creator:
Lietzke, M. P.
System:
The UNT Digital Library
Fabrication Development of UO2-Stainless Steel Composite Fuel Plates for core B of the Enrico Fermi Fast Breeder Reactor
Experimental work concerned with the development of an inexpensive composite fuel plate with a high burnup potential for application in a 500°C sodium environment as Core B of the Enrico Fermi Fast Breeder Reactor.
Date:
April 18, 1961
Creator:
Cherubini, J. H.; Beaver, R. J. & Leitten, C. F., Jr.
System:
The UNT Digital Library
Mathematics Panel: Annual Progress Report for Period Ending December 31, 1960
Programming research in the construction of a translator to Oracle language from ALGOL.
Date:
April 6, 1961
Creator:
unknown
System:
The UNT Digital Library
Sulfex Process: Engineering-Scale Semicontinuous Decladding of Unirradiated Stainless Steel-Clad UO2 and UO2-ThO2
An engineering-scale demonstration of the Sulfex process indicated that semi-continuous decladding of unirradiated stainless steel-clad UO2 or U02ThO2 fuels is feasible.
Date:
April 4, 1961
Creator:
Finney, B. C. & Hannaford, B. A.
System:
The UNT Digital Library
Homogeneous Reactor Project Quarterly Progress Report: November 1959-January 1960
From Summary: "The major objective of the run was the investigation of fuel stability. The reactor operated for long periods at the design power of 5 Mw with none of the usual indications of instability while the system pressure was kept at 1250 psig. Run 21 ended on January 22, so that the reason for an abrupt change in the mixing rate of fuel between the core and blanket could be investigated and a reactor steam-system valve could be repaired."
Date:
April 29, 1960
Creator:
Briggs, R. B.
System:
The UNT Digital Library
Nuclear Superheat Project Fabrication, Irradiation and Evaluation of Superheat Fuel Element SH-1 and SH-2
The fabrication, irradiation and evaluation of the first two superheat fuel assemblies is described in detail. Experimental data indicate that, in general, the nuclear superheat fuel elements have performed satisfactorily under the testing conditions used. Certain problem areas which will influence future fuel element designs have been defined.
Date:
April 7, 1960
Creator:
Lees, E. A.; Boyle, R. F. & Spalaris, C. N.
System:
The UNT Digital Library
Air Scattering of Co60 Gamma Rays: Theory Versus Experiment
For Co60 source at 15 meters, the air-scattered gamma dose rate predicted by theory is excerpted from ORNL-1575, pp. 167-203. This is compared with experimental measurements for the same source and comparable geometry reported by Convair in CVAC-170T. After applying an appropriate correction for ground scattering as estimated in Mart-55-16T (Convair), the two results are found to be in substantial agreement.
Date:
April 17, 1958
Creator:
Moran, Rubert S.
System:
The UNT Digital Library