[Aerosol Generator Design] : Letter Report (open access)

[Aerosol Generator Design] : Letter Report

The following report provides information on an aerosol generator fit to produce fine particles by a vaporization-condensation technique. Included is a diagram of the essential components of the generator.
Date: October 19, 1960
Creator: Rosinski, John & Stockham, John D.
System: The UNT Digital Library
Radiation Synthesis Involving Halogenated Compounds : Progress Report No. 2 Covering the Period From August 1, 1960 to October 31, 1960 (open access)

Radiation Synthesis Involving Halogenated Compounds : Progress Report No. 2 Covering the Period From August 1, 1960 to October 31, 1960

Report covering progress regarding a study on radiation synthesis involving halogenated compounds. Experimental progress, results and discussion are included.
Date: October 31, 1960
Creator: Glasson, W. A. & Feng, P. Y.
System: The UNT Digital Library
EURATOM PROGRAM "Improved Zirconium Alloys" (open access)

EURATOM PROGRAM "Improved Zirconium Alloys"

Introduction: "This report is an expanded version of the regular monthly letter report and is prepared in this form with the intention of reviewing work on the subject program for Euratom technical personnel. Work performed during the month of September, which normally constitutes the entire letter report, has been condensed under one heading."
Date: October 5, 1960
Creator: Weinstein, Daniel & Van Thyne, R. J.
System: The UNT Digital Library
A Feasibility Study for the Use of an Extended Pm¹⁴⁷ Source for Analytical Fluorescence Spectroscopy: Final Report (open access)

A Feasibility Study for the Use of an Extended Pm¹⁴⁷ Source for Analytical Fluorescence Spectroscopy: Final Report

From summary: The design of a spectrometer with the requisite improvement in crystals facilitates X-ray tube fluorescence.
Date: October 31, 1960
Creator: Brech, Frederick
System: The UNT Digital Library
An Evaluation of Fossil Superheat for Nuclear Power Plants (open access)

An Evaluation of Fossil Superheat for Nuclear Power Plants

From introduction: This report sets forth the results of a study of the evaluation of fossil fuel superheat in nuclear power plants.
Date: October 1960
Creator: unknown
System: The UNT Digital Library
Evaluation of Commercial Ceramic Coating for Short Time Protection of Columbium 1% Zirconium (open access)

Evaluation of Commercial Ceramic Coating for Short Time Protection of Columbium 1% Zirconium

Abstract. Fourteen commercial enamel frits from five different manufacturers were tested to determine their abilities to protect Nb-1% Zr during the forging cycle in the temperature range of 1800 to 2300 deg F. One frit was found to afford good coverage and protection at 2200 deg F at times up to 5 hours of exposure. Adherence was excellent during upset forging of a coated Nb--1% Zr sample heated 45 minutes at 2200 deg F. Another frit afforded good protection and coverage at 1700 deg F. (auth)
Date: October 10, 1960
Creator: McGrath, D. W.
System: The UNT Digital Library
Boiling Heat Transfer of Liquid Metals: a Literature Search (open access)

Boiling Heat Transfer of Liquid Metals: a Literature Search

This partially annotated bibliography contains references on boiling heat transfer of liquid metals. Emphasis is place on boiling heat transfer of liquid sodium, liquid potassium, and liquid rubidium. The period covered is 1950 to date. References are arranged alphabetically by title. Sources used in compiling this bibliography are: Abstracts of Classified Reports, Nuclear Science Abstracts.
Date: October 3, 1960
Creator: Cernak, Elizabeth A.
System: The UNT Digital Library
Military Field Expedient Shielding Experiment (open access)

Military Field Expedient Shielding Experiment

Convair-Fort Worth, under contract to the U.S. Army Engineer Research and Development Laboratories, performed experiments to obtain data for use in applying field materials to shield portable nuclear-reactor power plants.
Date: October 18, 1960
Creator: Wheeler, D. M. & Bostick, L. H.
System: The UNT Digital Library
ABWR: PL-2 Design Report (open access)

ABWR: PL-2 Design Report

From preface: This report satisfies the quarterly progress report requirements for PL-1 and PL-2 plant design work for the period ending September 30, 1960 At present time a SL-1 Core 2 is under construction. This is a replacement core for SL-1 (ALPR) and will be identical to a PL-2 core; a PL condenser is under test at the SL-1 facility; final construction plans for PL components and modules which are not site sensitive will be completed in March 1961.
Date: October 15, 1960
Creator: Combustion Engineering, inc. Nuclear Division.
System: The UNT Digital Library
Structural Response and Permanent Displacement Measurements (open access)

Structural Response and Permanent Displacement Measurements

Measurements and visual observations made during the Hardtack II series of underground shots provide basis for conclusions regarding shock-resistant design of protection for cavities in rock and qualitative prediction of permanent displacements in rock due to nuclear detonations. Vibration measurements on blast-resistant construction in soil provided non-nuclear test results which apply to shock resistant design. With varying soil cover, the compressive mode predominated in arch structures and a mass of soil apparently acted with the structure that varied in magnitude in inverse fashion with two depths of cover. Underground structural harmonic response theories were in part verified, for some structures, though the absence of an appreciable flexural mode in buried arch structures was significant.
Date: October 28, 1960
Creator: Sievers, R. H., Jr. & Stacy, A. R.
System: The UNT Digital Library
The Preparation of a Set of BeO-Based Fuel Element Specimens for the H.T.G.C. Irradiation Programme (open access)

The Preparation of a Set of BeO-Based Fuel Element Specimens for the H.T.G.C. Irradiation Programme

Ceramic fuel element specimens consisting of a uranium oxide-thorium oxide solid solution dispersed in beryllium oxide were fabricated by hot pressing in graphite dies. Details of fabrication techniques are given. Tests for overall composition, homogeneity and size and shape of fuel grains made during and at the completion of the work indicate that the specimens are in general agreement with initial specifications.
Date: October 1960
Creator: Reeve, K. D.
System: The UNT Digital Library
Heat Treatment and Properties of Iron and Steel (open access)

Heat Treatment and Properties of Iron and Steel

From Abstract: "This Monograph has been prepared to give an understanding of heat treatment principally to those unacquainted with this subject. This Monograph has been prepared to answer such inquiries and to give in simplified form a working knowledge of the basic theoretical and practical principles involved in the heat treatment of iron and steel."
Date: October 3, 1960
Creator: Digges, Thomas G. & Rosenberg, Samuel J.
System: The UNT Digital Library
Health and Safety Laboratory Fallout Program Quarterly Summary Report: June 1, 1960 - September 1, 1960 (open access)

Health and Safety Laboratory Fallout Program Quarterly Summary Report: June 1, 1960 - September 1, 1960

Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.
Date: October 1, 1960
Creator: Hardy, Edward P., Jr.; Rivera, Joseph & Frankel, Robert
System: The UNT Digital Library
Analysis of Zero Power Experiments on SM-1 Core II and SM-1A Core I (open access)

Analysis of Zero Power Experiments on SM-1 Core II and SM-1A Core I

Abstract: An analysis of SM-1 Core II and SM-1A Core I zero power experiments was made by comparing these cores to each other and to AM-1 Core I on the basis of critical bank positions, bank calibrations and available chemical analyses of the fuel plate compositions. The effects of replacing boron absorbers by europium absorbers upon rod worth and stuck rod conditions were studied. Comparisons of measured and calculated power distributions were made. It was concluded that both SM-1 Core II and SM-1A Core I contain nearly identical B-10 loading of 17.79 grams, compared to the best estimate of 15.75 grams for SM-1 Core I. The available data indicates that all three cores possess similar nuclear characteristics.
Date: October 5, 1960
Creator: Paluszkiewicz, S.
System: The UNT Digital Library
Neutron Spark Counter (open access)

Neutron Spark Counter

Technical report. From Abstract : "Spark counters of the wire plate type are rugged and simple, and their sensitivity is directly proportional to the specific ionization of incident particles. Spark counters are insensitive to beta and gamma radiation but readily respond to alpha particles. With a suitable converter, the spark counter can also be employed as a neutron counter. Spark counters thus appear to be very good candidates for the measurement of neutron flux at reactor startup, where the high background of gamma radiation can be troublesome to other types of counters. A spark counter of cylindrical geometry was built and shown to have adequate sensitivity and stability for such duty."
Date: October 1960
Creator: Caiati, Frank P.
System: The UNT Digital Library
Correction to the Debye-Huckel Theory (open access)

Correction to the Debye-Huckel Theory

In a recent paper, Bowers and Salpeter described a method for calculating the correlation energy of a classical one-component electron gas. The same problem has been considered by Meeron, Friedman, and Abe, using methods involving the summation of cert infinite classes of diagrams. While the relation between these theories and that of Bowers and Saltpeter is not year clear, it is interesting to note that Abe obtained an equivalent expression by approximating an integral. We have calculated the contribution to the equation of state using Abe's original expression and we found that the equation is valid only for certain values and it gives a correction of the wrong sign. On the other hand, our results are comparable to those which Bowers and Salpeter obtain from higher approximations.
Date: October 7, 1960
Creator: Trulio, John G.
System: The UNT Digital Library
An Experimental Check On The Range-Energy Curve Of Pions In Propane (open access)

An Experimental Check On The Range-Energy Curve Of Pions In Propane

The kinetic energies of pions from radioactive decays in propane have been determined by using the information given by the angles of the secondary particles. This method is independent of any range-energy relation.
Date: October 24, 1960
Creator: Patrick, Jack W.
System: The UNT Digital Library
The RCA 6949 As A Self-Excited Cyclotron Oscillator (open access)

The RCA 6949 As A Self-Excited Cyclotron Oscillator

The oscillator of the 88-in. cyclotron which is being built in Berkeley is tunable from 5.3 to 16.5 Mc. It delivers a maximum c-w power of 300 kw. At the rated doc voltage of 75 kv the resonator stores 4.5 joules of electrical energy. The transients produced by this amount of energy, during sparking, place unusual requirements upon the design of the oscillator tube. The features of the RCA 6949 which make it particularly well-suited to this type of application are discussed in this paper. Other topics covered are the oscillator anode power supply, the hard-tube modulator, protective equipment, and oscillator instrumentation.
Date: October 25, 1960
Creator: Smith, Bob H.
System: The UNT Digital Library
A Preliminary Investigation Of The System Time Spread For Some Types Of Multiplier Phototubes (open access)

A Preliminary Investigation Of The System Time Spread For Some Types Of Multiplier Phototubes

A preliminary investigation of four types of multiplier phototubes under conditions simulating their use in scintillation and Cerenkov nuclear detectors is described. The investigation involves time-spread and rise-time measurements at different reference points on the outpost pulses, as well as observations of some special characteristics of these tubes.
Date: October 1960
Creator: El Hakim, Yahia
System: The UNT Digital Library
Hazards Evaluation Report Associated with the Operation of EBWR at 100 MW (open access)

Hazards Evaluation Report Associated with the Operation of EBWR at 100 MW

From Introduction: "This hazards report covers the basic modifications to the EBWR plant as designed to increase the present operating design rating of 20 Mwt to a new rating of 100 Mwt. it is written as a supplement to ANL-5781 (the original hazards report) and follows the outline of that report for purposes of cross reference."
Date: October 1960
Creator: Wimunc, E. A. & Harrer, J. M.
System: The UNT Digital Library
Specific Heats and Enthalpies of Technical Solids at Low Temperatures: A Compilation from the Literature (open access)

Specific Heats and Enthalpies of Technical Solids at Low Temperatures: A Compilation from the Literature

Report giving tables of the specific heat, cp, and the enthalpy of 28 metals, 3 alloys, 8 other inorganic substances, and 8 organic substances in the temperature range, 1º to 300º K.
Date: October 3, 1960
Creator: Corruccini, Robert J. & Gniewek, John J.
System: The UNT Digital Library
Notes on Lattice Parameter Calculations (open access)

Notes on Lattice Parameter Calculations

In the last two or three years there has been a notable improvement in the knowledge and understanding of reactor lattice physics. During this interval, measurements of parameters have been improved and the methods of analysis have been greatly strengthened. It has become apparent that the classical ways for computing the lattice parameters are not sufficient. It is the purpose of this report to publish under one cover as much of the most recent information as possible.
Date: October 6, 1960
Creator: Joanou, G. D.
System: The UNT Digital Library
9-ANGIE : a Two-Dimensional, Multigroup, Neutron-Diffusion-Theory Reactor Code for the IBM 709 or 7090 (open access)

9-ANGIE : a Two-Dimensional, Multigroup, Neutron-Diffusion-Theory Reactor Code for the IBM 709 or 7090

The 9-ANGIE, one of a series of reactor neutronic programs for an IBM 709 or 7090 data processing system, solves the time-dependent, multi-group, neutron diffusion equation for one to eighteen energy groups applied to a rectangular mesh superimposed on either an x-y or an r-z plane. It is characterized by its generalities in region description, boundary conditions, etc., without sacrificing simplicity of input preparation and ease of machine operation. The notation, the style, and the format have been held as consistent as possible with 9-ZOOM, the companion one-dimensional program.
Date: October 28, 1960
Creator: Stone, Stuart P.
System: The UNT Digital Library
Decoupling Concepts and Project Cowboy (open access)

Decoupling Concepts and Project Cowboy

This paper for the Project Vela Technical Symposium is intended to be a brief resume of the principle results of the Cowboy program. The material is taken from a report entitled "Use of Large Cavities to Reduce Seismic Waves from Underground Explosions" by Herbat, Werth, and Spring (1960). As a result, no effect is made to justify each step in the analysis; reference should be made to the complete report.
Date: October 11, 1960
Creator: Werth, Glenn C.
System: The UNT Digital Library