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5,469 Matching Results
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Refinements of the Theory of the Infinitely-Long, Self-Acting, Gas-Lubricated Journal Bearing. Interim Report
The lubrication equations for an arbitrary Newtonian fluid are derived directly from the general equations for conservation of mass, momentum, and energy. From the lubrication equations an inequality is obtained for the internal film temperature rise, after which the isothermal film equations are derived. Then, for perfectly-aligned self-acting journal bearings, a conservation equation is obtained. For gas bearings this condition gives: [formula] constant along the axis of the bearing. Application of this condition to the infinitely-long gas bearing gives more accurate pressure solutions for this case. The Katto-Soda form of the differential equation for the infinitely-long bearing is solved by a series expansion in the eccentricity ratio, the first terms of which give the original, approximate Katto-Soda solution. In addition, solutions obtained numerically by digital computations are presented in graphical and tabular form for eccentricity ratios from 0 to 0.9 and compressible bearing parameter [formula]. Design charts based on these calculations are provided.
Date:
January 1960
Creator:
Elrod, Harold G., Jr.
Object Type:
Report
System:
The UNT Digital Library
Attempts to Delineate Inborn Anemias in Mice. Progress Report and Fifth Renewal Proposal, Report Period: January 10, 1959-January 31, 1960. Renewal Period: May 1, 1960-April 30, 1961
During the past year, three papers covering results of a major series of experiments on intergenotype of blood-forming tissue have appeared, demonstrating successful implantation of isologues normal cells in anemic hosts, permanently correcting their genetic defect in hematopoiesis, both with and without irradiation of the host. Heavy host irradiation was shown ineffective as preparations for implantation of homologous cells of widely different antigenic types.
Date:
February 16, 1960
Creator:
Russell, Elizabeth Shull, 1913-2001
Object Type:
Report
System:
The UNT Digital Library
A Survey of Non-Fuel-Bearing Materials for the Marine Gas-Cooled Reactor
Results of an initial examination of non-fuel-bearing materials for the Marine Gas Cooled Reactor are presented. Areas given specific attention include structural and cladding materials and graphite moderator. Other areas not included because of classification include zirconium hydride moderator and control materials. In each report section, available pertinent information is summarized and a plan for future work is given.
Date:
May 1, 1958
Creator:
Bokros, J. C.; Dijkstra, L; & Merten, U.
Object Type:
Report
System:
The UNT Digital Library
Progress letter No. 11 for January 1, 1960 through January 31, 1960
A stainless steel autoclave for superheated water corrosion test was installed and "conditioned". Tests were begun to investigate the feasibility of densifying slip cast stainless steel by means of liquid phase sintering. Attempts to prepare tubular fuel elements by vacuum forming were resumed. Although thick-walled vacuum formed casting have been sintered on the aluminum mandrels without cracking, this has not yet been accomplished with the think sections of interest.
Date:
February 15, 1960
Creator:
Baron, Edeard H.
Object Type:
Report
System:
The UNT Digital Library
Shock Hydrodynamics of an Exploding Steam Pressure Vessel : Final Report
Initially issued as a brief survey of the shock problems associated with an assumed failure of a pressurizer vessel in a vapor container, this paper contains more detailed calculations and considerations of the analysis present in the original study.
Date:
November 25, 1955
Creator:
Porzel, F. B.
Object Type:
Report
System:
The UNT Digital Library
The Preliminary Shield Design for the 50 MW Commercial Reactor
The investigation in this report were conducted to determine the required shielding to reduce radiation to a workable level, to determine the heeating in the various core components so coolant flow rates could be determined, and to determine the thermal stress and temperature distribution in the structural and load bearing members.
Date:
December 18, 1958
Creator:
Bagley, R. O., Jr.
Object Type:
Report
System:
The UNT Digital Library
Primary Shielding Calculations on the IBM 650 (ROC Codes)
In order to calculate the gamma dose rates in the primary shielding of thermal reactors, four programs were written for thew IBM 650 computer.
Date:
October 15, 1958
Creator:
Rosen, S. S.; Oby, P. V. & Caton, R. L.
Object Type:
Report
System:
The UNT Digital Library
Thermal Design Criteria for APPR Pressurized Water Reactors
The following criteria have been established for thermal design of APPR pressurized-water reactors in this study
Date:
November 26, 1958
Creator:
Love, J.
Object Type:
Report
System:
The UNT Digital Library
Material Specifications for APPR-1 Core II Control Rod Fuel Elements and Absorber Sections
The specifications reported in this study are based on the results of development performed at Oak Ridge National Laboratory under the supervision of the Metallurgy Division.
Date:
December 30, 1958
Creator:
Edgar, E. C. & Robertson, R. D.
Object Type:
Report
System:
The UNT Digital Library
Lovely-1, Program No. 55, Thermal Analysis on the IBM 650
This program is intended to be utilized for the establishment of flow requirements of a tailored flow core.
Date:
November 26, 1958
Creator:
Love, J. D. & Stueck, C. J.
Object Type:
Report
System:
The UNT Digital Library
IBM 650 Computer, Program Number 755, Collation of ROC Code Output
Using the output of programs 653 and 654, each card of which contains the dose information for one dose point at one energy, program 655 produces the sum of the dose values of all energies for one dose point
Date:
December 19, 1958
Creator:
Stueck, C. J.
Object Type:
Report
System:
The UNT Digital Library
Reactivity of Substitution Elements
A method is sought for predicting the reactivity differences between fuel elements attached to control absorbers and fixed fuel elements
Date:
January 19, 1959
Creator:
Murray, R. L., Dr.
Object Type:
Report
System:
The UNT Digital Library
Rolling and Welding Type 430M Tubes to Stainless Steel Overlaid Carbon Steel Tubesheets
In the fabrication of the steam generator on APPR-1A it was considered necessary to roll the Type 430M tubes into carbon steel tube-sheets. The rolled joint was a necessary precaution to prevent secondary water from contacting the stainless steel weld.
Date:
February 16, 1959
Creator:
Bennett, R. W.; Meister, R. P. & Kerton, R. J.
Object Type:
Report
System:
The UNT Digital Library
The Design, Installation, and Testing of the Gas-Cooled Reactor UOâ‚‚ Irradiation Experiment at the NRTS
Report regarding sixteen experiments performed with a miniature re-entrant gas loop. Includes design problems and difficulties encountered, as well as their solutions.
Date:
September 8, 1961
Creator:
Porter, E. H.
Object Type:
Report
System:
The UNT Digital Library
Uranium Occurrences, Fall River Area, Clear County, Colorado [Fiche]
This report describes the Fall River Area that was examined for favorable areas between known occurrences of pitchblende at Quartz Hill and at Lawson.
Date:
October 16, 1951
Creator:
Smith, Loren E. & Baker, Kenneth E.
Object Type:
Report
System:
The UNT Digital Library
Drilling at Temple Mountain, San Rafael Swell, Emery County, Utah [Fiche]
This report describes two drilling projects that were successful in discovering ore deposits at Temple Mountain.
Date:
August 1952
Creator:
Anderson, Andrew H. & Miller, Richard D.
Object Type:
Report
System:
The UNT Digital Library
Uranium Occurrences, Fall River Area, Clear Creek County, Colorado
Discussing occurrences of uranium in the Fall River Area of Clear County, Colorado
Date:
October 16, 1951
Creator:
Smith, Loren E. & Baker, Kenneth E.
Object Type:
Report
System:
The UNT Digital Library
Drilling at Green Vein Mesa, Emery County, Utah
Discussing diamond drilling carried out at Green Vein Mesa in the San Rafael Swell.
Date:
unknown
Creator:
Miller, Richard D. & Rogers, Kenneth J.
Object Type:
Report
System:
The UNT Digital Library
Thermal Stress Testing of SM-2 Fuel Elements : Final Report January 1, 1959 to July 1, 1960
Thermal stress testing was performed on portions of reactor fuel elements.
Date:
September 20, 1960
Creator:
Christenson, J. A. & Kortheuer, J. D.
Object Type:
Report
System:
The UNT Digital Library
Summary of Reactor Design Information from Three Years Operation of a Small PWR
Reactor design information obtained from three years' operation of a small pressurized water reactor, the SM-1 (formerly APPR-1), presented and discussed
Date:
September 9, 1960
Creator:
Gallagher, J. G.
Object Type:
Report
System:
The UNT Digital Library
Structural Testing of SM-2 Fuel Elements
Ability of the originally designed SM-2 stainless steel fuel elements, of both tungsten inert gas (TIG) and electrical resistance welded construction, to withstand static transverse pressure gradients of normal reactor operation was investigated
Date:
September 29, 1960
Creator:
Coleman, F. G., Jr. & Herbert, R. J.
Object Type:
Report
System:
The UNT Digital Library
SM-1 Research and Development Quarterly Report : April 1 to June 30, 1960
This report covers research conducted at the SM-1 and highlights progress made in plant water chemistry and health physics practices and progress on individual tasks and test are reported
Date:
September 20, 1960
Creator:
Bergman, C. A.
Object Type:
Report
System:
The UNT Digital Library
Nuclear Analysis of Various Spert-III Critical Experiments
The calculational models employed in the nuclear analysis of the SM-2 were applied to various critical experiments performed upon the SPERT-III core
Date:
April 27, 1961
Creator:
Paluszkiewica, S.
Object Type:
Report
System:
The UNT Digital Library
Activity Build-Up Control by High pH Coolant : A Literature Survey
A survey was made of unclassified literature dealing with the control of activity buildup in pressurized water reactors by high pH coolants
Date:
January 23, 1961
Creator:
Bergen, C. R.
Object Type:
Report
System:
The UNT Digital Library