A Rapid Beam Deflector for the Brookhaven AGS (open access)

A Rapid Beam Deflector for the Brookhaven AGS

An air cored pulse deflection coil has been constructed for the Brookhaven AGS. The system produces a deflecting pulse with a peak radial deflection of 2.5 cms and duration of 70 microseconds. Beam spill duration of 15 to 50 microseconds from the target is readily achieved. One deflector has given satisfactory service for over a year and a second unit has been installed this summer.
Date: October 2, 1962
Creator: Brown, H. N.; Culwick, B. B. & Forsyth, E. B.
System: The UNT Digital Library
The Hydrolysis of the Rare-Earth Carbides (open access)

The Hydrolysis of the Rare-Earth Carbides

From introductory paragraph: "This report concerns the hydrolysis of rare-earth dicarbides, sesquicarbides, solid solutions of carbon in rare-earth metals as well as rare-earth carbon alloys of varying compositions. Many of the carbide samples used in this study were those which had been studied by Gschneider (9)(7) and had been preserved in evacuated, sealed tubes. Some additional preparations of the sesquicarbides were made especially for these studies. The hydrolytic reactions were carried out in water and hydrochloric acid solutions of varying concentrations. Assay of the gaseous products was by mass spectrometry and gas chromatography. Both instruments were carefully calibrated with pure hydrocarbons and hydrogen and mixture thereof."
Date: July 2, 1962
Creator: Svec, Harry J. (Harry John), 1918-; Capellen, Jennings & Saalfeld, Fred E.
System: The UNT Digital Library
The Half-Life and Gamma Ray Abundance of Cs-137 (open access)

The Half-Life and Gamma Ray Abundance of Cs-137

The nuclide Cs-137 is a fission product commonly used for measurement of uranium burnup in irradiated uranium fuel by the fission product to uranium ratio method. In the application of this method, the largest single error introduced in the measurement of burnup is the uncertainty in the half-life of Cs-137. Because of the uncertainty in this value and its importance in nuclear fuel burnup analysis, a reinvestigation was undertaken to obtain a more accurate value using the mass spectrometric method.
Date: June 2, 1962
Creator: Rider, B. F.; Peterson, J. P. & Ruiz, C. P.
System: The UNT Digital Library
Radiation Patterns in the Lower Ionosphere and Fresnel Zones for Elevated Antennas Over a Spherical Earth (open access)

Radiation Patterns in the Lower Ionosphere and Fresnel Zones for Elevated Antennas Over a Spherical Earth

From Introduction: "The purpose of this work is to give the results of a detailed computation of antenna patterns in the ionosphere at VHF over a spherical earth."
Date: April 2, 1962
Creator: Merrill, R. G. & Mansfield, W. V.
System: The UNT Digital Library
Simple High-Voltage Trapezoidal Pulse Generator (open access)

Simple High-Voltage Trapezoidal Pulse Generator

From abstract: "A description is given of a simple circuit used to produce negative voltage pulses up to 60 kilovolts with a portion rising with constant slope up to 10 kilovolts per microsecond."
Date: April 2, 1962
Creator: Gonella, Luigi
System: The UNT Digital Library
Strontium-90 Fueled Thermoelectric Generator Power Source for Five-Watt U.S. Coast Guard Light Buoy: Final Report (open access)

Strontium-90 Fueled Thermoelectric Generator Power Source for Five-Watt U.S. Coast Guard Light Buoy: Final Report

From summary: This report describes the 10-watt Sr-90 thermoelectric generator, the dc-to-dc converter, batteries and the method of installation in the light buoy.
Date: February 2, 1962
Creator: unknown
System: The UNT Digital Library
Determination of Diffusion Cooling in Graphite by Measurement of the Average Neutron Velocity (open access)

Determination of Diffusion Cooling in Graphite by Measurement of the Average Neutron Velocity

From Abstract: "The diffusion cooling coefficient in graphite has been determined by measuring the change in the asymptotic average velocity with buckling, by pulsed neutron methods. The times necessary to establish equilibrium spectra in graphite and heavy water have been measured and are reported."
Date: January 2, 1962
Creator: Starr, E. & De Villiers, J. W. L. (Jacobus Wynand Louw)
System: The UNT Digital Library
High Performance UO2 Program Third Quarterly Progress Report: October-December 1961 (open access)

High Performance UO2 Program Third Quarterly Progress Report: October-December 1961

The primary purpose of this joint USAEC-Euratom program is to obtain a better understanding of the maximum achievable operating characteristics of UO2 as a reactor fuel. During the program work will be performed in two areas that have been of concern to reactor core designers for a long time, namely, fission gas release and central melting in fuel rods.
Date: January 2, 1962
Creator: Weidenbaum, B.
System: The UNT Digital Library