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The Ductility of Brazed Stainless Steel Joints (open access)

The Ductility of Brazed Stainless Steel Joints

Abstract: "The ductility of Type 310 stainless steel T-joints brazed with GE-62 brazing alloy was measured at room temperatures 1200, 1650, and 1800 F. The measure of ductility was taken as the plastic axial strain required to crack braze fillets in T-section tensile specimens. At elevated temperatures, the ductility of as-brazed joints approximated that of the stainless steel, but at room temperature the brazed joints had only one-tenth the ductility of the base metal. Annealing for 16 hr at 1800 F in air was found to triple the room-temperature ductility of the brazed joint."
Date: July 8, 1953
Creator: Saller, Henry A.; Stacy, J. T. & Eddy, N. S.
System: The UNT Digital Library
A Proposed Particle Containment Device (open access)

A Proposed Particle Containment Device

Abstract: A device is proposed for confining charged particles to a localized region of space by means of the alternating electric field of a resonant cavity. The motion of single electrons in the field is stable. The limitations to particle density and temperature are discussed, and found to be too severe to allow the device to serve as a reactor, although it might be a useful laboratory tool.
Date: July 8, 1953
Creator: Good, Myron L.
System: The UNT Digital Library
Dependence of Positive Pion Production Cross Sections on Atomic Number at Low Energies (open access)

Dependence of Positive Pion Production Cross Sections on Atomic Number at Low Energies

A preliminary study of positive pion production from proton-nucleus collisions revealed that positive pion production cross sections agree more favorably with a Z 2/3 variation than with a variation proportional to the atomic number. A similar study on negative pion production has shown that negative pion yields from proton-nucleus collisions tend to vary in proportion to the number of neutrons in the nucleus. As a result an experiment was performed to investigate if there is a significant change in positive pion production with changing atomic number at two lower pion energies.
Date: September 8, 1953
Creator: Sagane, Ryokichi, 1905-1969 & Dudziak, Walter F.
System: The UNT Digital Library
Fused Salt Mixtures as Potential Liquid Fuels for Nuclear Power Reactors (open access)

Fused Salt Mixtures as Potential Liquid Fuels for Nuclear Power Reactors

From introduction: "This report summarizes the work done on a study of fused-salt systems in a search for new liquid fuels suitable for use in a nuclear power reactor."
Date: September 8, 1953
Creator: Crooks, R. C.; Snyder, M. J. & Clegg, J. W.
System: The UNT Digital Library
Use of Commercial Grade Methane in ASP Counting Instruments (open access)

Use of Commercial Grade Methane in ASP Counting Instruments

The gas commonly used in the chamber of the Simpson Proportional Alpha Counter (ASP) is the high grade, 99% pure methane. The cost of the gas has often raised the question of finding an adequate substitute and a number of substitutions have been attempted. Commercial methane has been substituted successfully for 99% pure methane and its use is recommended in ASP counters. Neither commercial nor technical methane caused any significant changes in instrument operation.
Date: October 8, 1953
Creator: Rasmussen, M. J.
System: The UNT Digital Library
Welded Closures for Fuel Elements (open access)

Welded Closures for Fuel Elements

From abstract: "The inert-gas metal-arc welding process was used to determine weldability studies of various aluminum alloys that are being considered for use as can materials. The solid-phase and induction welding processes were also investigated for making can closures."
Date: October 8, 1953
Creator: Sopher, R. P.; Martin, G. E.; Grable, G. B.; Voldrich, C. B.; Leatherman, A. F. & Todd, F. C.
System: The UNT Digital Library
MTA Progress Report for June through November, 1953 (open access)

MTA Progress Report for June through November, 1953

Introduction: "This report covers the contributions of UCRL to MTA research and development program during the period June 1 to November 30, 1953. In this program UCRL continues to work in close collaboration with the California Research and Development Company (CRD)."
Date: February 8, 1954
Creator: Lawrence Radiation Laboratory
System: The UNT Digital Library
Age Calculations for Lattices with Aluminum-Matrix Slugs (open access)

Age Calculations for Lattices with Aluminum-Matrix Slugs

The process of age calculation for Hanford exponential lattices containing aluminum-matrix slugs, where the sums run over the materials of the lattice cell.
Date: June 8, 1954
Creator: Neumann, Herschel
System: The UNT Digital Library
A New System for Catalytic Recombination of Hydrogen and Oxygen (open access)

A New System for Catalytic Recombination of Hydrogen and Oxygen

This report follows an investigation with the purpose of studying the operational characteristics of a catalytic tube recombiner where the gases are passed over stainless steel tubes coated with platinum black.
Date: October 8, 1954
Creator: Miraldi, F. D.; Billerbeck, C. J.; Delicate, W. S. & Farquhar, J., III
System: The UNT Digital Library
Machine Calculations for the Analysis of the Plane Immobilized Plasma by Trajectories (open access)

Machine Calculations for the Analysis of the Plane Immobilized Plasma by Trajectories

Abstract: "The analysis of an immobilized plasma by trajectories for the Cartesian case has been adapted to machine calculation and the results of such calculations are described. Their most surprising features is the thinness of the transition layer between a vacuum and a uniform plasma, which is possible without assuming too extreme physical circumstances."
Date: March 8, 1955
Creator: Tonks, Lewi, 1897-1971 & Keirstead, Ralph
System: The UNT Digital Library
Air Leakage Through Labyrinth Seals (open access)

Air Leakage Through Labyrinth Seals

This report contains the results of tests which demonstrated the feasibility of using graphite labyrinth type seals, i.e., a bushing machined with alternate grooves and lands on the inside diameter to create a sufficient pressure drop to provide a satisfactory seal.
Date: April 8, 1955
Creator: McCarthy, P. B.
System: The UNT Digital Library
Final Report of Stainless Steel Connector Evaluation (open access)

Final Report of Stainless Steel Connector Evaluation

The primary objective of the tests described herein was to determine if the standard five bend connector (drawing H-1-23475) and/or the T. F. Robinson three bend connector (drawing SK-1-20855) fabricated from Type 304 stainless steel tubing would satisfy the requirements of the K reactors. Results of the tests show that the standard five bend connector made from Type 304 stainless steel 0.065 inch wall tubing, in the as bent condition, with either cadmium plated Parker brass nuts and sleeves or cadmium plated high carbon steel nuts and sleeves, is suitable for installation of the K reactors.
Date: July 8, 1955
Creator: Mansius, C. A. & Spink, J. R.
System: The UNT Digital Library
Status Report on the K-4 Magnetic Induction Machine (open access)

Status Report on the K-4 Magnetic Induction Machine

Due to laboratory interest in devices capable of production of high current with short rise times in gaseous discharges (plasmas), an experimental machine has been built and tested to obtain data applicable to the design of a high gradient magnetic induction machine. This machine consists of a condenser type energy storage bank air core coupled to a toroid in which the plasma is produced. It has been used to determine circuit parameters and the effect of these parameters on the plasma.
Date: August 8, 1955
Creator: Baggett, L. M.; Franklin, T. L. & Van Duren, A.
System: The UNT Digital Library
The Coulometric Titration of Plutonium (open access)

The Coulometric Titration of Plutonium

This work was performed to develop a general chemical method for the determination of small amounts of plutonium in solution. The work showed that a coulometric titration based on the preliminary oxidation of the plutonium to Pu (VI) followed by titration with electrolytically-generated ferrous ion to Pu (IV) was such a general method and was subject to few interferences. The significance of the work is that a chemical determination of plutonium can be made for amounts of plutonium heretofore determined only by radioassay methods, and the chemical determination of larger amounts are made more readily and with higher precision than with previous methods. The work also extends the application of coulometric titration methods to a new substance.
Date: September 8, 1955
Creator: Carson, Jr., W. N.; Gile, H. S. & Vanderwater, J. W.
System: The UNT Digital Library
Statistical Analysis of Run to Rupture Tests Involving More Than Two Metal Types (open access)

Statistical Analysis of Run to Rupture Tests Involving More Than Two Metal Types

In the reference document, a statistical method for analyzing run to rupture tests involving two metal types, a test material and a control standard, is presented. It often happens that more than two metal types are involved in a production test. In this document, the statistical procedure recommended for this situation is presented.
Date: November 8, 1955
Creator: Jaech, J. L.
System: The UNT Digital Library
An Investigation of Scaling of Zirconium at Elevated Temperatures : Quarterly Status Report No. 10; Sept. 2, 1955 to Dec. 2, 1955 (open access)

An Investigation of Scaling of Zirconium at Elevated Temperatures : Quarterly Status Report No. 10; Sept. 2, 1955 to Dec. 2, 1955

As previously reported, zirconium undergoes large dimensional increases after scaling in air in a critical temperature range, 700 degree-1050 degree C. This finding was observed with specimens of a constant thickness (0;062 in.) To study the thickness effect, a number of specimens ranging in thickness from 0.020 to 0.200 in. were scaled in air at a temperature (900 degree C) where the growth is a maximum for a given time. Both cold rolled iodine sheet and forged iodide bar stock were used. to determine the effect of orientation, specimens from the forged bar were obtained such that the scaling surface was either parallel to or perpendicular to the long axis of the bar.
Date: December 8, 1955
Creator: Barrett, Charles A.; Evans, E. B. & Baldwin, W. M., Jr.
System: The UNT Digital Library
Remotely Operated Irradiation Facility : (Sample Carrier) (open access)

Remotely Operated Irradiation Facility : (Sample Carrier)

Report discussing a possible solution for providing a remotely operated way of handling samples at an irradiation facility. Explanation of operating requirements, equipment, and a possible layout is included.
Date: December 8, 1955
Creator: Fox, J. C.
System: The UNT Digital Library
Test of Water Quality Velocity on Pitting of 72-S Aluminum (open access)

Test of Water Quality Velocity on Pitting of 72-S Aluminum

Report discussing a test aimed at determining if high velocity water could cause severe pitting in 72-S aluminum. This test was designed after an increase in the amount of pitting-caused water leaks in reactors.
Date: December 8, 1955
Creator: Houck, William C.
System: The UNT Digital Library
Application and Operation of the 325 Building Well Counter (open access)

Application and Operation of the 325 Building Well Counter

Well-type scintillation counters have found use in many radiochemical laboratories. A gamma scintillation well counter has been used to measure the gamma activity of liquid samples in the 325 Building counting room for about a year. This well counter has been built and calibrated so that gamma activity measurements made with it can be easily compared with measurements made with the gamma scintillation counter (GSC). The well counter is electronically identical to the present GSC and differs only in the shape of the crystal used and the physical arrangement of the lead shield. The crystal contains a well which allows a tube containing the sample to be inserted in the crystal. The physical arrangement of the detector greatly simplifies the preparation of liquid samples for activity measurement. The 325 Building well counter and its application to chemical research and plant process analysis will be discussed in the following paragraphs. An operating procedure is also included.
Date: March 8, 1956
Creator: Brauer, F. P.
System: The UNT Digital Library
Technical Information for Application of Differential Pressure Transmitters in Pulse Column Bottom Interface Control Systems (open access)

Technical Information for Application of Differential Pressure Transmitters in Pulse Column Bottom Interface Control Systems

The information in this report is based on experience with a similar unit installed on experimental pule columns in the 321 Building. These installations were made to demonstrate the feasibility of the system. In one case, the installation on the 2A Prototype Column, the differential pressure cell (D/P cell) bottom interface control system was monitored by a capacitance-type instrument. The other installations were made on glass columns and were monitored visually.
Date: October 8, 1956
Creator: Smith, A. E.
System: The UNT Digital Library
HRT Source Shield Calculations (open access)

HRT Source Shield Calculations

Calculations indicate that the proposed shielding arrangement will give a dose rate at the surface of the water tank of about 100 mrem per hr., practically all gammas. This is adequate for transportation and handling, but if the radiation actually proves to be this high, a storage location isolated from normal working areas must be provided. The isolation area need not be large, however, since the calculated dose rate at 10 feet from the shielded sources is only 3.5 mrem pr hr. For the short time required to transfer the source from the water tank into the reactor the Pb carrier alone will provide sufficient shielding. At one meter from the source shielded by the Pb carrier, the dose rate is estimated to be 170 mrem per hr., with neutrons contributing he major part. With reasonable care, the operations should be carried out without excessive exposures. The results of the calculations are summarized.
Date: January 8, 1957
Creator: Haubenreich, P. N. & Rivenbark, G. W.
System: The UNT Digital Library
Beehive and Hornet : Reactor Codes for Spherical Geometry (open access)

Beehive and Hornet : Reactor Codes for Spherical Geometry

Abstract: Beehive is a five energy group, two region, time independent spherical reactor code. It considers the problem of reactor system in which the core material is assumed to be at a higher energy (temperature) than the reflector material. The code obtains a closed solution for the critical reactor assembly by a procedure which is a logical extension of normal two group theory. The companion code, Hornet, computes the neutron fluxes for the critical assembly determined by the Beehive calculation. Both codes have been programmed for the IBM Magnetic Drum Data-Processing Machine, Type 650. The codes, together with the flow diagrams, are included with this report.
Date: February 8, 1957
Creator: Stone, Stuart P.
System: The UNT Digital Library
Extraction of Metal Ions with Di-2-Ethylhexyl Phosphoric Acid (open access)

Extraction of Metal Ions with Di-2-Ethylhexyl Phosphoric Acid

Blake and his co-workers have shown that uranium and other elements can be extracted from acid solutions by various type of organo-phosphorous compounds. Early investigations in the laboratory have demonstrated the applicability of tri-n-alkyl phosphine oxides to the extraction of metal ions from acidic solutions for analytical purposes. This paper is concerned with a similar qualitative investigation of the extraction of metal ions with a di-alkyl phosphoric acid, di-2-ethylhexyl phosphoric acid (D2EPHA).
Date: February 8, 1957
Creator: Ross, W. J. & White, J. C.
System: The UNT Digital Library
Fuel Costs in Batch- and Continually-Processed Homogeneous Reactors (open access)

Fuel Costs in Batch- and Continually-Processed Homogeneous Reactors

The fuel requirement of a heavy-water moderated, homogenous, power reactor were estimated for a variety of initial loadings, for both bath and continuous methods of fuel removal. This study considered a 12-ft spherical reactor, temperature 250 C, 500 Mw thermal power, 125 Mw electrical power capability, 0.8 load factor, and 4%/year inventory charges for U and D2O. The fuel shipping-and-processing charges were assumed to be $1/gm of fissionable fuel for the "batch" processed reactors, and $0.37/gm for the "continuous" processed reactors, Under these conditions, the minimum fuel costs associated with a 10-year 'batch" operating period were about 1.8 or 3.1 mills/kw-hr, if highly enriched U cost $15/gm or $20/gm, respectively. the analogous costs for the "continuous" processed reactor were about 1.6 and 2.6 mills/kw-hr, respectively.
Date: February 8, 1957
Creator: Kasten, Paul R. & Aven, R. E.
System: The UNT Digital Library