Study of Remote Military Power Applications: Report 5, NORAD (open access)

Study of Remote Military Power Applications: Report 5, NORAD

From introduction: The study is essentially an economic evaluation of the construction and operation of nuclear power plants at several designated military installations where increased power generating capabilities of 5 to 40 mwe may be required by the Government during the period 1963 through 1970.
Date: July 1960
Creator: unknown
System: The UNT Digital Library
Study of Remote Military Power Applications: Report 7, Super Sage Rocky Mountains Area (open access)

Study of Remote Military Power Applications: Report 7, Super Sage Rocky Mountains Area

From introduction: The study is essentially an economic evaluation of the construction and operation of nuclear power plants at several designated military installations where increased power generating capabilities of 5 to 40 mwe may be required by the Government during the period 1963 through 1970.
Date: July 1960
Creator: unknown
System: The UNT Digital Library
9-Zoom : A One-Dimensional, Multigroup, Neutron Diffusion Theory Reactor Code for the IBM 709 [Supplement] (open access)

9-Zoom : A One-Dimensional, Multigroup, Neutron Diffusion Theory Reactor Code for the IBM 709 [Supplement]

The following document describes the usage of the LRL 9-ZOOM code, a neutron diffusion theory reactor code for the IBM 709. The code has been modified to solve configuration of a series of stacked cylindrical disks, designating a new geometry case.
Date: July 12, 1960
Creator: Stone, S. P.
System: The UNT Digital Library
Reactor Grade Zircaloy-2 Ingot (open access)

Reactor Grade Zircaloy-2 Ingot

Scope. This specification covers ingots of zirconium alloy designated as Zircaloy-2, and intended for the production of reactor components.
Date: July 15, 1960
Creator: Perryman, E. C. W.
System: The UNT Digital Library
Zircaloy-2 Wire Material (open access)

Zircaloy-2 Wire Material

Scope. This specification covers Zircaloy-2 wire material for reactor use where high integrity and satisfactory corrosion resistance at elevated temperatures are required.
Date: July 15, 1960
Creator: Perryman, E. C. W.
System: The UNT Digital Library
Zircaloy-2 Tubing for Fuel Sheathing (open access)

Zircaloy-2 Tubing for Fuel Sheathing

Scope. This specification covers Zircaloy-2 tubing, both seamless and welded, for reactor fuel rod sheathing where high integrity, and satisfactory corrosion resistance at elevated temperatures ae required.
Date: July 15, 1960
Creator: Perryman, E. C. W.
System: The UNT Digital Library
Zircaloy-2 Sheet and Strip Material (open access)

Zircaloy-2 Sheet and Strip Material

Scope. This specification covers Zircalogy-2 sheet and strip material for reactor use where high integrity and satisfactory corrosion resistance at elevated temperatures are quired.
Date: July 15, 1960
Creator: Perryman, E. C. W.
System: The UNT Digital Library
Estimating Safety Probabilities from Fallout Forecasts for Nevada Test Site (open access)

Estimating Safety Probabilities from Fallout Forecasts for Nevada Test Site

Abstract: "Available data on wind persistence and wind forecasting capability have been applied in estimating the probability of a fallout pattern shifting from an uninhabited safe sector into a populated region. Safety probability is computed from win variability, forecasting accuracy, initial height and particle size of radioactivity landing at a point in the predicted fallout pattern, predicted wind speed, length of forecast period, and safe-sector angular width."
Date: July 1, 1960
Creator: Reed, Jack W.
System: The UNT Digital Library
A Study of Nevada Test Site Wind Variability (open access)

A Study of Nevada Test Site Wind Variability

Abstract: "Wind observations collected at Yucca Flat since 1951 are analyzed for timewise variability. Variability functions of altitude, season, wind speed, and vector wind are described. Derived variability parameters are incorporated into calculations of fallout safety probability for NTS operations."
Date: July 1, 1960
Creator: Reed, Jack W.
System: The UNT Digital Library
Geology of the Michigan Basin with Reference to Subsurface Disposal of Radioactive Wastes (open access)

Geology of the Michigan Basin with Reference to Subsurface Disposal of Radioactive Wastes

From introduction: The purpose of this report is to describe the geology of the rocks in the different sedimentary basins in relation to problems of disposal of liquid radioactive wastes in the ground.
Date: July 1960
Creator: de Witt, Wallace, Jr.
System: The UNT Digital Library
Stability for inhomogeneous difference schemes (open access)

Stability for inhomogeneous difference schemes

Abstract. The Equivalence Theorem of P. Lax is extended to difference schemes for initial-value problems for linear inhomogeneous PDE with linear inhomogeneous boundary values and for boundary-value problems.
Date: July 13, 1960
Creator: Seidman, Thomas I.
System: The UNT Digital Library
Project Cowboy : Physical Properties of Salt Samples (open access)

Project Cowboy : Physical Properties of Salt Samples

The purpose of Project Cowboy was to investigate the seismic signals generated by chemical explosions in underground cavities, with particular emphasis on the possibility of decoupling of these signals from the surrounding media. The project site was the Carey Salt Company salt mine, located approximately five miles west of Winnfield, Louisiana. The tests were run during fiscal year 1960. This report presents the results of tests performed on specimens from the samples of salt taken in the area.
Date: July 15, 1960
Creator: Guido, Raymond S. & Warner, Stanley E.
System: The UNT Digital Library
A Study of Heat and Mass Transfer to Uninsulated Liquid Oxygen Containers (open access)

A Study of Heat and Mass Transfer to Uninsulated Liquid Oxygen Containers

The wide use of liquid oxygen as an oxidant in rocket engines has resulted in an increased interest in low-temperature heat transfer. Storage tanks for this type of application, being uninsulated, contain a boiling-liquid low-temperature sink, which is susceptible to environmental heat inputs and subsequent liquid loss by vaporization. Such losses are difficult to predict due to the complex combination of ambient conditions which exist, and the lack of knowledge concerning their combined effects. Heat transfer in this field is difficult to analyze primarily because of its transient nature. This is a result of such factors as: (1) the growth of an insulating frost layer on the outer surface of the container, with its accompanying energy transfer to the system; (2) the temperature dependent convective air pattern that surrounds the container, (3) the transfer of radiant energy to the system, and (4) the mechanical failure of the frost itself with subsequent sloughing from the container wall. A lack of knowledge regarding the coefficient of diffusion of water vapor through air and the thermal conductivity of frost in this depressed temperature range further complicates the predictions of heat transfer.
Date: July 20, 1960
Creator: Holten, David Charles
System: The UNT Digital Library
PCTR Measurement of EGCR Control Rod Worth (open access)

PCTR Measurement of EGCR Control Rod Worth

This paper describes the measurement of control rod strength in the PCTR. The first section outlines the theory and method of such a measurement, and the second section presents the results of the measurement of the Experimental Gas Cooled Reactor (EGCR) control rod strength. The reactor parameter actually inferred is the difference in the infinitive multiplication factor for a control rod supercell with and without the control rod in place in the supercell. These measurements are, therefore, very closely related to the measurement of k∞ for an ordinary lattice cell.
Date: July 20, 1960
Creator: Nichols, P. F.; Engesser, F. C. & Oakes, T. J.
System: The UNT Digital Library
Critical Tests for PRT Reactor (open access)

Critical Tests for PRT Reactor

This document authorizes the performance in accordance with the specifications noted, the PRTR Critical Tests described herein. The experiments described have the following objectives:
Date: July 1, 1960
Creator: Triplett, J. R.; Anderson, J. K.; Peterson, R. E.; Regimball, J. J.; Russell, J. T.; Schmid, L. C. et al.
System: The UNT Digital Library
Use Of Pyroelectric Devices For Measuring Small Temperature Changes (open access)

Use Of Pyroelectric Devices For Measuring Small Temperature Changes

A technique for measuring extremely small temperature changes by means of a pyroelectric device is described. The sensing element is a short thin rod of polarized barium titanate ceramic with electrodes on the ends. The electric charges produced by changes in temperature are measured by a vibrating-reed electrometer. A number of calorimetric and noncalorimetric applications for the device are suggested.
Date: July 1960
Creator: Lang, Sidney B.
System: The UNT Digital Library
Portable Radiation Instrumentation Standardization (open access)

Portable Radiation Instrumentation Standardization

This development work was undertaken to investigate and standardize scintillation detector and transistorized circuitry techniques in instruments used for detecting and measuring alpha and beta particles, gamma photons, and both slow and fast neutrons. At the present time, the standard radiation detection instrumentation used at Hanford employ vacuum-tube circuitry with typical detectors being ion chambers, G-M tubes, HF3 tubes, etc. The vacuum tubes require excessive battery power, and some of the circuits are adversely affected by humidity and temperature conditions.
Date: July 1, 1960
Creator: Spear, W. G.
System: The UNT Digital Library
Reactor-Grade Zircaloy-4 Ingot (open access)

Reactor-Grade Zircaloy-4 Ingot

Scope. This specification covers ingots of zirconium alloy designated as Zircaloy-4, and intended for the production of reactor components.
Date: July 15, 1960
Creator: Perryman, E. C. W.
System: The UNT Digital Library
Zircaloy-4 Wire Material (open access)

Zircaloy-4 Wire Material

Scope. This specification covers Zircaloy-4 wire material for reactor use where high integrity and satisfactory corrosion resistance at elevated temperatures are required.
Date: July 15, 1960
Creator: Perryman, E. C. W.
System: The UNT Digital Library
Zircaloy-4 Sheet and Strip Material (open access)

Zircaloy-4 Sheet and Strip Material

Scope. This specification covers Zircaloy-4 sheet and strip material for reactor use where high integrity and satisfactory corrosion resistance at elevated temperatures are required.
Date: July 15, 1960
Creator: Perryman, E. C. W.
System: The UNT Digital Library
A Note on the Optical Potential with the Pauli Principle (open access)

A Note on the Optical Potential with the Pauli Principle

Abstract. The idea of determining potentials from phase shifts is here called the "optical model" while the construction of an effective single particle scattering potential from the known two-body forces is called the "optical potential." A novel method is given for construction of the optical potential with the Pauli principle and its difficulties are pointed out. In the Appendix one connection between the optical potential and optical model is given.
Date: July 1960
Creator: Mittleman, Marvin H.
System: The UNT Digital Library
Stresses and Deflection in a Cylindrical Shell Subjected to Concentrated Radial Loads (open access)

Stresses and Deflection in a Cylindrical Shell Subjected to Concentrated Radial Loads

Abstract. The measured stresses and deflections of cylindrical shells with free ends, when subjected to concentrated loads along the central diameter, are presented. An empirical analog is made with a simply supported flat plate for which stresses and deflection are easy to compute. Over the range of parameters studied (ratio of cylinder diameter to wall thickness varied from 32 to 64, ratio of cylinder length to diameter varied for. 0.6 to 5) the agreement is such that the empirical results should have useful application in the design of shells for local loading.
Date: July 1960
Creator: Steidel, Robert F., 1926- & Galasso, Maurice
System: The UNT Digital Library
Silver Bromide Crystal Size Distribution as Influenced by Gelatin Concentration in Producing Nuclear Emulsion (open access)

Silver Bromide Crystal Size Distribution as Influenced by Gelatin Concentration in Producing Nuclear Emulsion

At the Montreal colloquium Ahmed urged Oliver to make batches of emulsion which would differ only in gelatin concentration. At that meeting Oliver had reported finding a correlation between grain size and silver ion concentration during precipitation, as implied by Perfilov and his Leningrad colleagues. Ahmad felt that one should have more precise knowledge of the relative influence of gelatin concentration of grain sized and their distribution. The incentive is that, in spite of excellent progress in many laboratories and in consistently dependable production from industry (to us, of course, Ilford is most familiar), nuclear emulsions are needed in a wider variety of sensitivities and grain sizes. Available nuclear emulsions have limitations in sensitivity, discriminatory ability, and concentration of hydrogen nuclei. Fine grain size enhances discriminatory ability. An incentive is also in that there is a shortage of literature dealing with the processes involved in the fundamental steps of emulsion production.
Date: July 1, 1960
Creator: Oliver, Albert J. & Ahmad, Ishfaq
System: The UNT Digital Library
Explosives :a Bibliography (open access)

Explosives :a Bibliography

This bibliography is selective, unclassified, and covers the period 1950 - April 1960. Sources consulted were the following: Applied Science and Technology Index (Industrial Arts Index), Chemical Abstracts, Engineering Index, U.S. Atomic Energy Commission Nuclear Science Abstract, Armed Services Technical Information Agency Title Announcement Bulletin, and Publisher's Catalogs.
Date: July 1960
Creator: Wenrich, Carl J.
System: The UNT Digital Library