Fabrication of Yankee Core I Prototype Fuel Element (open access)

Fabrication of Yankee Core I Prototype Fuel Element

Introduction: Development of a process for manufacturing fuel elements for the Yankee reactor and fabrication and testing of a prototype assembly is reported.
Date: May 1960
Creator: D'Amore, M.
Object Type: Report
System: The UNT Digital Library
The High Intensity Food Irradiator: Report 17 (open access)

The High Intensity Food Irradiator: Report 17

From introduction: A thorough investigation, both experimental and theoretical was carried out on plaque type radiators. Five phases of the work are reported: preliminary design analysis, experimental measurements, computational program and analytical studies, followed by a general discussion of source design principles. The results are summarized in graphs and formulae which may be applied to other design requirements.
Date: May 1, 1960
Creator: Curtiss-Wright Corporation
Object Type: Report
System: The UNT Digital Library
Liquid Metal Fuel Reactor Experiment: Operation and Testing of a Nonnuclear Liquid-Metal System (open access)

Liquid Metal Fuel Reactor Experiment: Operation and Testing of a Nonnuclear Liquid-Metal System

Extensive experimental program undertaken to provide data on the operation and testing of a bismuth-to-bismuth dual-loop system.
Date: May 1960
Creator: unknown
Object Type: Report
System: The UNT Digital Library
OMR Degasifier Loop Experiment (open access)

OMR Degasifier Loop Experiment

Abstract: A loop has been constructed to study the removal of water and highly volatile materials from Organic Moderated Reactor coolant by vacuum degasification. An analysis of the process was made to determine the most important parameters for study during the experimental program.
Date: May 1, 1960
Creator: Corporales, G. W. & Benson, P. R.
Object Type: Report
System: The UNT Digital Library
OMRE Fuel Plate Surface Temperature Measurement (open access)

OMRE Fuel Plate Surface Temperature Measurement

Abstract: Accurate measurement of OMRE fuel-element surface temperatures is important for evaluation of the performance of organic compound as moderator and coolant materials in nuclear reactors; a mixture of polyphenyls has been used in reactor operation to-date.
Date: May 1, 1960
Creator: Sudar, S.
Object Type: Report
System: The UNT Digital Library
Piqua Prototype Handling System (open access)

Piqua Prototype Handling System

Abstract: Equipment has been developed to handle the fuel elements and control rods for the Piqua (OMR) reactor.With the handling machine, which consists of a shielded cask mounted on a gantry, a fuel element can be replaced in the core in about 27 minutes.
Date: May 1960
Creator: Nadler, H.
Object Type: Report
System: The UNT Digital Library
Plutonium: Enriched OMR Cores (open access)

Plutonium: Enriched OMR Cores

Abstract: The influence of plutonium on the nuclear characteristics of organic moderated cores is studied.
Date: May 1, 1960
Creator: Connolly, T. J.
Object Type: Report
System: The UNT Digital Library
Radium and Mesothorium Poisoning and Dosimetry and Instrumentation Techniques in Applied Radioactivity (open access)

Radium and Mesothorium Poisoning and Dosimetry and Instrumentation Techniques in Applied Radioactivity

"The study of the toxicity of Ra and MsTh(Ra/sup 228/) in humans was continued. Several Thorotrast cases were also examined. Physical and clinical studies were made on 151 persons. In all cases possible gamma ray measurements were made of Ra and MsTh decay products retained in the body, alpha -ray measurements of Rn and Rn/sup 220/ in breath, a complete medical history was taken, a complete x-ray examination was made of the skeleton, and urinalysis, hematological, and blood chemistry studies were made."
Date: May 1960
Creator: Evans, Robley D.
Object Type: Report
System: The UNT Digital Library
Scale "Up or Down" Analysis for Prototype Test (open access)

Scale "Up or Down" Analysis for Prototype Test

Introduction: In conjunction with the final design and development of a 70 MW sodium intermediate heat exchanger and a sodium steam generator, an analysis is required which can be used as a basis for a determination to scale up or scale down the designs. Included in this analysis are those considerations leading to the recommendation of the best prototype test unit and to some of the limits imposed on scaling up or down when considering future applications of designs other than those actually tested. In addition, these considerations include aspects required to accurately predict the performance, operation, mechanical reliability, and feasibility of fabrication of the 70 MW design.
Date: May 1, 1960
Creator: Alco Products (Firm).
Object Type: Report
System: The UNT Digital Library
Thermal Cycling and Leakage Tests of 12-inch Valves for Sodium Service (open access)

Thermal Cycling and Leakage Tests of 12-inch Valves for Sodium Service

Abstract: Tests were performed to determine the effect of thermal cycling on the across-the-seat leakage characteristics of commercially available valves considered for use in the sodium coolant system of the Hallam Nuclear Power Facility.
Date: May 1, 1960
Creator: Baroczy, C. J.
Object Type: Report
System: The UNT Digital Library
Preliminary petrographic study of rock from Nevada Test Site - Basalt Mesa (open access)

Preliminary petrographic study of rock from Nevada Test Site - Basalt Mesa

Discussing photographs of rocks from Basalt Mesa
Date: May 6, 1960
Creator: Anderson, E. E.
Object Type: Report
System: The UNT Digital Library
The ML-1 Design Report (open access)

The ML-1 Design Report

From abstract: "This report describes the design of the mobile nuclear power plant which is to be the prototype of a mobile, low-powered nuclear power plant intended to furnish electrical power in remote locations."
Date: May 16, 1960
Creator: Linenberger, G. A.
Object Type: Report
System: The UNT Digital Library
Effect of Superheat and Moisture Separation on the SM-2 Design (open access)

Effect of Superheat and Moisture Separation on the SM-2 Design

From abstract: "The study evaluates the utilization of superheat and moisture separation techniques in the SM-2 design to improve the steam plant reliability and thermal efficiency. Ease of packaging, steam plant transient response, and capital costs are also considered. The reference design used for comparison is the steam cycle employing saturated steam at 600 psia described in APAE No. 40, Volume II."
Date: May 27, 1960
Creator: Phelps, E. F.
Object Type: Report
System: The UNT Digital Library
Interim Report of Nuclear Analysis Performed on SM-2 Core and Vessel : September 1, 1958 to December 31, 1959. (open access)

Interim Report of Nuclear Analysis Performed on SM-2 Core and Vessel : September 1, 1958 to December 31, 1959.

Abstract: This technical report contains a description of the nuclear analysis performed upon the SM-2 core and vessel for the period September 1, 1958 to December 31, 1959. Calculations are given for core reactivity, power distributions, lifetime, reactor control, kinetics, radiation problems, fuel and poison burn-ups, and the nuclear effects of poisons, temperature, and geometry. Wherever possible, experimental data is included in order to test the validity of the analytical models. The SM-2 nuclear analysis was performed by Alco Products, in. under Tasks 1, 8, and 10 of Contract No. AT(30-2)-326 for the Atomic Energy Commission.
Date: May 27, 1960
Creator: Bobe, P. E.; Birken, S. H.; Byrne, B. J.; Clancy, E. F. & Fried, B. E.
Object Type: Report
System: The UNT Digital Library
Design and Properties of a Neon Filled Spark Chamber in a Magnetic Field (open access)

Design and Properties of a Neon Filled Spark Chamber in a Magnetic Field

Introduction: Recently a new type of charged particle detector, the so-called spark chamber, has been developed. The detector has certain advantages in high energy physics over bubble chambers aside from its much lower cost.
Date: May 1, 1961
Creator: Heyn, Maarten P.
Object Type: Thesis or Dissertation
System: The UNT Digital Library
Development of a Gas Injector System for Homogeneously Labeling Gas Storage Reservoirs (open access)

Development of a Gas Injector System for Homogeneously Labeling Gas Storage Reservoirs

"The laboratory experiments and field testing which were carried out in the development of a homogeneous gas labeling device are described. Detailed drawings of the injector and its most critical components are included. Recommendations are made for a production model of the device along with estimated costs of construction."
Date: May 1, 1961
Creator: Sewell, Curtis & Schulz, Isidor
Object Type: Report
System: The UNT Digital Library
Heat Transfer Coefficients with Annular Flow During "One-Through" Boiling Water to 100 Per Cent Quality at 800, 1100, 1400 PSI (open access)

Heat Transfer Coefficients with Annular Flow During "One-Through" Boiling Water to 100 Per Cent Quality at 800, 1100, 1400 PSI

From introduction: "Once-Through boiling of water to 100 per cent steam quality was successfully accomplished. Results of Departure from Nucleate Boiling, transition, and film boiling tests are presented."
Date: May 1, 1961
Creator: Polomik, E. E.; Levy, S. & Sawochka, S. G.
Object Type: Report
System: The UNT Digital Library
High Dilution On-Stream Isotopic Tracers Annual Report: 1961 (open access)

High Dilution On-Stream Isotopic Tracers Annual Report: 1961

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: May 1961
Creator: Aebersold, Paul C. & Bizzell, Oscar M.
Object Type: Report
System: The UNT Digital Library
Inelastic Proton-Proton Scattering At 1.3 Bev (open access)

Inelastic Proton-Proton Scattering At 1.3 Bev

"The understanding of interactions between the elementary particles, which no number thirty, and range from the massless neutrino to the Е with a mass of approximately 1320 Mev, in a prerequisite to the knowledge of the structure of matter. Although the complex aggregate of elementary particles which constitute matter displays properties different from those of the basic building blocks, nevertheless it is impossible to gain a firm knowledge of the behavior of matter without first ascertaining in the intrinsic properties of elementary particles, as well as the dynamics of their interactions. The present work is concerned with inelastic proton-proton scattering at 1.35 Bev, where single pion production predominates."
Date: May 1961
Creator: Hien, Nguyen Chi
Object Type: Report
System: The UNT Digital Library
Iteration Methods for Non-Linear Problems (open access)

Iteration Methods for Non-Linear Problems

The methods of successive displacements or relaxation methods are investigated for a class of nonlinear problems. In particular it is shown that these methods are applicable to a large class of nonlinear problems arising from variational problems which yield elliptic equations. Constructive existence and uniqueness theorems are presented for the discrete problem and criteria are given for a practical method of obtaining solutions. The example of a discrete Plateau problem is used to illustrate the feasibility of the results. The processes are also shown to apply to uniformly elliptic problems.
Date: May 1, 1961
Creator: Schechter, Samuel
Object Type: Report
System: The UNT Digital Library
Some Computational Methods for the Study of Diatomic Molecules (open access)

Some Computational Methods for the Study of Diatomic Molecules

"The present work describes some computer-oriented techniques for the application of the laws of quantum mechanics to the problems of determining basic structure of diatomic molecules. At times, calculations of the type described here yield results which can be compared directly with experiment to check the validity of the hypotheses and technique used they may predict the results of unobserved experimental phenomena; and, in many instances, they provide quantities which are necessary for the interpretation of experimental data but which cannot be directly measured."
Date: May 1, 1961
Creator: Cooley, James W.
Object Type: Report
System: The UNT Digital Library
Uranium-Bismuth In-Pile Corrosion Test Loop: Radiation Loop No. 1 (open access)

Uranium-Bismuth In-Pile Corrosion Test Loop: Radiation Loop No. 1

Report issued by the Brookhaven National Laboratory discussing uranium-bismuth corrosion test loops. Design, construction, and operation of the test loops are presented. This report includes tables, illustrations, and photographs.
Date: May 1961
Creator: Waide, C. H.; Kukacka, L. E.; Meyer, R. A.; Milau, J.; Klein, J. H.; Chow, J. G. Y. et al.
Object Type: Report
System: The UNT Digital Library
Utilization of Radiactive Isotpoes in Coal Process Research (open access)

Utilization of Radiactive Isotpoes in Coal Process Research

"This is the fourth Quarterly Report on Task II dealing with Methods Development for Radio-Tracing of Coal Product Hydrocarbons With Tritium. The problem of radio-chemical purity of traces is resolved by developing a new method of labeling with tritium that generates essentially no highly tagged side products or impurities."
Date: May 1, 1961
Creator: Yavorsky, P. M. & Gorin, E.
Object Type: Report
System: The UNT Digital Library
Description of Method for Determining Geometric Parameters of Surfaces in Contact (open access)

Description of Method for Determining Geometric Parameters of Surfaces in Contact

"A method and equipment are described for determining the surface parameters of contact required for heat transfer calculations. In this method, the output of a surface analyzer for one surface is recorded on one channel of magnetic tape and the output for the other surface of the contact pair on a second channel. The tape is played back to an analog computer which then integrates the analog voltage to compute the void volume thickness, the number of contact points, and the ratio of metallic contact area to the total area."
Date: May 2, 1961
Creator: unknown
Object Type: Report
System: The UNT Digital Library