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Determination of Heavy Water Purity by Infrared Absorption (open access)

Determination of Heavy Water Purity by Infrared Absorption

The practical application of heavy water purity determination by infrared absorption spectroscopy using standard laboratory equipment was demonstrated in connection with the operation of heavy water-moderated Special Power Excursion Reactor Test (SPERT II) Facillty at the NRTS. (auth)
Date: January 16, 1962
Creator: Abernathey, R. M. & Morgan, T. D.
System: The UNT Digital Library
Abilene Fire Department Annual Report: 1962 (open access)

Abilene Fire Department Annual Report: 1962

Annual report of the Abilene Fire Department describing the organization and administration, with updates on goals, activities, and accomplishments during fiscal year 1962.
Date: 1962
Creator: Abilene (Tex.). Fire Department.
System: The Portal to Texas History
Analysis of Electric Energy Usage in Air Force Houses Equipped with Air-to-Air Heat Pumps (open access)

Analysis of Electric Energy Usage in Air Force Houses Equipped with Air-to-Air Heat Pumps

From Introduction: "One part of this study, which is presented in this Monograph, consists of an analysis of electric energy usage and electric power demand data obtained from a sample group of occupied houses at Little Rock Air Force Base in Arkansas, equipped with heat pumps, water heaters, cooking ranges, clothes dryers, and miscellaneous appliances all operated by electricity."
Date: July 13, 1962
Creator: Achenbach, Paul R.; Davis, Joseph C. & Smith, William T.
System: The UNT Digital Library
Some fundamental aspects of vaporization (open access)

Some fundamental aspects of vaporization

A discussion of the fundamental aspects of vaporization is presented along with a discussion of evaporation within the theories of solids and gases. Suggestions are offered as to where assumptions might be introduced to describe the phenomenon more completely, and tenative definitions concerning factors which can give rise to vaporization coefficients are given. An effort is made to unify these concepts within the phenomenological framework of irreversible thermodynamics. (J.R.D.)
Date: December 1, 1962
Creator: Ackermann, R. J.; Thorn, R. J. & Winslow, G. H.
System: The UNT Digital Library
SNAP re-entry orbit; comments on the atmospheric entry and discussion of a proposed test (open access)

SNAP re-entry orbit; comments on the atmospheric entry and discussion of a proposed test

In order to evaluate entry into the atmosphere of an oblate (equatorial bulge) earth a standard atmosphere was used in conjunction with the standard rotating oblate spheroid. The density variation encountered in any one polar orbit around the earth will vary by about a factor of ten, due to oblateness. Therefore, the important effects on the re-entry trajectory are atmospheric density and oblateness of the earth. The SNAP configuration burn up characteristics will differ considerably between the steep (6/sup 0/) entry of the NASA Scout test and the orbital decay trajectory. However, the test can verify heat transfer rates on the actual configuration, and by proper calculation of material response, the actual decay breakup prediction can be improved.
Date: August 3, 1962
Creator: Ackermann, W. O.; Arthur, P. D. & Nelson, D. K.
System: The UNT Digital Library
ISOTROPIC HYPERFINE ENERGY OF INTERACTION OF FREE RADICALS IN SOLUTION (open access)

ISOTROPIC HYPERFINE ENERGY OF INTERACTION OF FREE RADICALS IN SOLUTION

None
Date: August 1, 1962
Creator: Acrivos, J. V.
System: The UNT Digital Library
Experimental Determination of Contact Conductance for Some Stainless Steel Contacts (open access)

Experimental Determination of Contact Conductance for Some Stainless Steel Contacts

"Contact conductances for three semi-smooth and rough stainless steel contacts involving six steels are determined. The procedure and equipment used are fully described, and the results are given. Graphs display thermal conductance and conductivity versus pressure and temperature."
Date: July 1962
Creator: Adamantiades, Achilles
System: The UNT Digital Library
COMPARATIVE COST STUDY OF PROCESSING STAINLESS STEEL-JACKETED UO$sub 2$ FUEL: MECHANICAL SHEAR-LEACH VS SULFEX-CORE DISSOLUTION (open access)

COMPARATIVE COST STUDY OF PROCESSING STAINLESS STEEL-JACKETED UO$sub 2$ FUEL: MECHANICAL SHEAR-LEACH VS SULFEX-CORE DISSOLUTION

The economics of mechanical shear-leach and Sulfex decladding-core dissolution head end treatments for processing typical tubular bundles of stainless steel-jacketed UO/sub 2/ nuclear fuels were compared. A 2.66 metric ton U/day head end portion of a plant was designed for each process and capital and operating costs were developed. For plants of this size and larger, mechanical shear-leach processing has the advantage of ~20% lower capital cost and 50% lower operating cost. Processing costs of stainless steel-jacketed UO/ sub 2/ by the Sulfex and shear-leach methods, including amortization and waste disposal but excluding solvent extraction, were .78 and 7l/kg U, respectively. Storage of stainless steel waste produced by the shear-leach method is less costly by a factor of 20 than for Sulfex. (auth)
Date: April 23, 1962
Creator: Adams, J. B.; Benis, A. M. & Watson, C. D.
System: The UNT Digital Library
Comparative Cost Study of Processing Stainless Steel-Jacketed UO2 Fuel: Mechanical Shear-Leach vs Sulfex-Core Dissolution (open access)

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
Automatic processing system for film badges (open access)

Automatic processing system for film badges

A semiautomatic film badge system was developed to process dosimeter film faster and more reliably than the previously used manual method. The films are automatically loaded and unloaded from the badges and marked with identifying numbers, manually developed, and automatically read. The resultant information is punched into IBM cards. (auth)
Date: September 1, 1962
Creator: Adams, J. W.
System: The UNT Digital Library
Reactions of Preoxidized Beryllium Powder in Moist Carbon Dioxide (open access)

Reactions of Preoxidized Beryllium Powder in Moist Carbon Dioxide

Breakaway corrosion of Be in moist CO2 can be avoided if the Be is fabricated using preoxidized powder. The powder is preoxidized by heating in dry O/sub 2/. Preoxidation of Be powder was measured as a function of temperature and time of heating in O/sub 2/. The subsequent reactions of the preoxidized powder in moist CO/sub 2/ at 700 deg C were studied and the effect of increasing amounts of added oxide was measured. A model is proposed to explain the inhibition of corrosion by added oxide. (auth)
Date: June 1962
Creator: Adams, R. B.; Price, G. H. & Stuart, W. I.
System: The UNT Digital Library
Symbols for Instrument Flowsheets and Drawings. A Recommended System for Application to ORNL Instrument Work (open access)

Symbols for Instrument Flowsheets and Drawings. A Recommended System for Application to ORNL Instrument Work

Details concerning a recommended system of flow-plan symbols and drawings are given. The system is designed to identify the function of all major instrument components and to show schematically the operation of the instrument relative to the particular process. The system is used for identification and designation. (J.R.D.)
Date: June 19, 1962
Creator: Adams, R. K.; Davis, D. G.; Hyland, R. F. & Lieberman, B.
System: The UNT Digital Library
Symbols for Instrument Flowsheets and Drawings : a Recommended System for Application to ORNL Instrument Work (open access)

Symbols for Instrument Flowsheets and Drawings : a Recommended System for Application to ORNL Instrument Work

This report supersedes ORNL CF-57-2-1, which was an extension and revision of ORNL CF-54-6-72. Details concerning a recommended system of flow-plan symbols and drawing are given. The system is designed to identify the function of all major instrument components and to show schematically the operation of the instrument relative to the particular process. The system is used for identification and designation. The system is a modification of the Instrument Society of American Recommended Practice (RP 5.1).
Date: June 19, 1962
Creator: Adams, R. K.; Davis, D. G.; Hyland, R. G. & Lieberman, B.
System: The UNT Digital Library
Fuel Elements for the Argonne Advanced Research Reactor (open access)

Fuel Elements for the Argonne Advanced Research Reactor

The core design and the fuel element concept for the high-flux Argonne Advanced Research Reactor are presented. The core is cooled and moderated by light water and utilizes beryllium as a reflector. The fuel element assembly is rhomboidal in cross section and consists of 27 plates fastened together at their edges by dovetailed locking keys, and at each end by end fittings. Each fuel plate is 40 mils thick and contains a uniform dispersion of highly enriched UO/ sub 2/ particles, up to a maximum of 37 wt%, in a matrix of sintered stainless steel powder. A 5 mil thick stainless steel cladding is metallurgically bonded to each side of the fueled matrix. (N.W.R.)
Date: January 1, 1962
Creator: Adolph, N.R.; Silberstein, M.S. & Weinstein, A.
System: The UNT Digital Library
Basic and Applied Radiotracer Studies Annual Report: 1962 (open access)

Basic and Applied Radiotracer Studies Annual Report: 1962

Introduction: The primary objective of the work of this report was research and development leading to large-scale applications of low level isotope tracer technology.
Date: June 1962
Creator: Aebersold, Paul C. & Bizzell, Oscar M.
System: The UNT Digital Library
Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1962 (open access)

Army Gas-Cooled Reactor Systems Program Semiannual Progress Report: January 1 - June 30, 1962

Report documenting the progress of the Army Gas-Cooled Reactor Systems Program to develop a mobile, low-power, nuclear power plant for Military field operation.
Date: August 17, 1962
Creator: Aerojet-General Corporation
System: The UNT Digital Library
K-Reactor Retubing Program graphite temperature study (open access)

K-Reactor Retubing Program graphite temperature study

A project has been proposed and the funds allocated for the replacement of the central zone aluminum process tubes at both K Reactors with smooth bore zirconium process tubes of approximately the same outside diameter as the original tubes. Associated with this project is the problem of relieving the present graphite stack distortion in the vicinity of the process tube channels and counteracting or prereliving, at this time, the expected graphite stack distortion that, will take place over the next ten years. Such relief becomes increasingly important when it is realized that long reactor life is required for the zirconium tubes in order to justify the cost of the project. This justification is also based upon the ability to charge normal sized, self supported fuel elements during the reactor life of the tubes. Relieving the restrictions in the graphite process channels caused by stack contraction will be done by removing localized portions of the graphite from the tube blocks and trunion blocks with a guided cutting tool. This immediately brings up the question of graphite temperatures and the presently imposed maximum graphite in temperature limits. Combined coring and graphite stark distortion could result in excessive graphite temperatures or localized hot …
Date: December 26, 1962
Creator: Agar, J. D.
System: The UNT Digital Library
KER loop 1 tube temperatures (open access)

KER loop 1 tube temperatures

None
Date: October 1, 1962
Creator: Agar, J. D.
System: The UNT Digital Library
The Aqueous Coordination Chemistry of Beryllium and its Relation to Fuel Processing - a Literature Survey (open access)

The Aqueous Coordination Chemistry of Beryllium and its Relation to Fuel Processing - a Literature Survey

A survey of the aqueous coordination chemistry of beryllium is given. The possible use of coordination chemistry in the separation of beryllium from fission products is discussed, outlining methods for separation processes.
Date: November 1962
Creator: Aggett, J. (John)
System: The UNT Digital Library
Experimental Cesium Line Shapes (open access)

Experimental Cesium Line Shapes

In partially-ionized cesium plasmas above 10/sup 13/ ionscm/sup -3/, the plasma-broadened lines are easily measured and can be used as a simple diagnostic method for the determination of ion density, once the width versus ion density relationship is established either theoretically or experimentally. Measured line widths are presented and results are compared with theoretical widths. The profiles of various lines of the sharp, diffuse, and fundamental series lines of cesium were measured at known ion densities with a scanning monochromator on a hot-cathode parallel-geometry cesium diode. For each case, the ion density and the electron temperature were determined by measuring the intensity of the radiative recombination continuum. Line intensities gave independent measurements of temperature that were in agreement with electron temperatures, showing the existence of local thermodynamic equilibrium and providing a confirmation of ion density through the application of the Saha equation. Detailed results of line width measurements are presented for a range of plasma density from 3.2 x 10/sup 13/ to 1.6 x 10/sup 15/
Date: January 1, 1962
Creator: Agnew, L. & Summers, C.
System: The UNT Digital Library
Neutron Dosimetry in and Around Human Phantoms By Use of Nuclear Track Emulsion (open access)

Neutron Dosimetry in and Around Human Phantoms By Use of Nuclear Track Emulsion

The validity of the nuclear track emulsion technique for fast-neutron dosimetry is examined in the exposure of a human phantom to PuBe neutrons, Semiautomatic track scanning and high-speed data analysis obviate the major disadvantages of emulsion dosimetry, and allow the absolute differential proton track energy spectrum at various locations in the phantom to be obtained without a serious cost in time. From this are calculated the total absorbed local tissue dose due to proton recoils and the local thermal neutron intensity during irradiation.
Date: April 1962
Creator: Akagi, Hiroaki & Lehman, Richard L.
System: The UNT Digital Library
30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System (open access)

30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System

Final design for the 30 megawatt intermediate heat exchanger and steam generator.
Date: January 31, 1962
Creator: Alco Products (Firm)
System: The UNT Digital Library
30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System: Volume 2, Chemical and Stress Analysis (open access)

30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System: Volume 2, Chemical and Stress Analysis

Chemical engineering analysis and stress analysis for design of the 3 megawatt intermediate heat exchanger and steam generator for service with a liquid sodium heat transfer fluid.
Date: February 28, 1962
Creator: Alco Products (Firm)
System: The UNT Digital Library
30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System: Volume 4, Operation and Maintenance Procedures (open access)

30 Megawatt Heat Exchanger and Steam Generator for Sodium Cooled Reactor System: Volume 4, Operation and Maintenance Procedures

Operation and maintenance procedures for 30 megawatt heat exchanger and steam generator for sodium cooled reactor system.
Date: May 15, 1962
Creator: Alco Products (Firm)
System: The UNT Digital Library