630A Maritime Nuclear Steam Generator Scoping Study (open access)

630A Maritime Nuclear Steam Generator Scoping Study

From foreword: This report presents the results of a study of a nuclear steam generator which uses reactor technology during the aircraft nuclear propulsion program to produce superheated steam for marine propulsion.
Date: April 6, 1962
Creator: General Electric Company. Flight Propulsion Division.
System: The UNT Digital Library
ABWR Design and Development Quarterly Progress Report, January 1 Through March 31, 1962 (open access)

ABWR Design and Development Quarterly Progress Report, January 1 Through March 31, 1962

Quarterly design and development progress report on the activities of the Army Boiling Water Reactor (ABWR) Program.
Date: April 15, 1962
Creator: Combustion Engineering, inc. Nuclear Division.
System: The UNT Digital Library
Accurate Nuclear Fuel Burnup Analyses; First Quarterly Report, (December 1961 - February 1962) (open access)

Accurate Nuclear Fuel Burnup Analyses; First Quarterly Report, (December 1961 - February 1962)

The objective of the Accurate Nuclear Fuel Burnup Analyses program is to develop more accurate methods for burnup analysis for general use than the current method of analysis of Ca-137 or Sr-90. The program will require from three to five years of effort.
Date: April 1, 1962
Creator: Rider, B. F.
System: The UNT Digital Library
The Adsorption and Surface Reactions of Hydrocarbons on Clean Iridium (open access)

The Adsorption and Surface Reactions of Hydrocarbons on Clean Iridium

From abstract: "The adsorption of ethane, ethylene and acetylene on clean iridium in a field emission microscope has been found to cause characteristic changes in the work function of the iridium surface. Further changes, which are time and temperature dependent, result when such surfaces are heated. Flash filament experiments have shown that the changes in work function upon heating are due to desorption reactions and that the desorbed product consists principally of hydrogen. By assuming a linear relationship between surface coverage and work function, it has been possible to determine the desorption kinetics from the observed rates of work function change at various temperatures. The results are consistent with a mechanism involving stepwise surface dehydrogenation in which a pair of hydrogen atoms is removed from the hydrocarbon molecule in each step, followed by desoption of the adsorbed hydrogen. At very high temperatures the remaining carbon atoms are removed, presumably by evaporation."
Date: April 7, 1962
Creator: Arthur, John R., Jr. & Hansen, Robert S.
System: The UNT Digital Library
Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 1. Cost Analysis and Future Development (open access)

Advanced Indirect Cycle Water Reactor Studies for Maritime Applications: Part 1. Cost Analysis and Future Development

First part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. I-ii).
Date: April 1962
Creator: Combustion Engineering, inc. Nuclear Division.
System: The UNT Digital Library
Analysis of Coaxial Two-Terminal Conical Capacitor (open access)

Analysis of Coaxial Two-Terminal Conical Capacitor

From Abstract: "The electric field is plotted and its construction steps for axial symmetry are given."
Date: April 6, 1962
Creator: Selby, M. C.
System: The UNT Digital Library
The Application of Wax Laps to Vibratory Polishers (open access)

The Application of Wax Laps to Vibratory Polishers

From introduction: "In this paper the adaptation of the wax lab surface vibratory polisher is described. The wax lap requires little maintenance during the life of the lap. It is not necessary to remove any of the holding devices on the bowl to clean and recondition the lap. The bowl is merely washed out, recharged and placed in operation. The wax lap will not wrinkle or tear, nor is it necessary to change it each day such as the silk or nylon cloths."
Date: April 19, 1962
Creator: Hopkins, E. N. & Peterson, D. T.
System: The UNT Digital Library
Boiling Potassium Heat Transfer Project Loop Design and Development (open access)

Boiling Potassium Heat Transfer Project Loop Design and Development

This technical report reviews the general purposes and immediate goals of the Heat Transfer Group at BNL's study of the heat transfer characteristics of alkali metals with phase change in forced convective flow. This report also presents a brief description of the design and development of the test loop. Figures detailing findings accompany the report.
Date: April 30, 1962
Creator: Chen, John C., 1934-2013
System: The UNT Digital Library
The Brookhaven Chemonuclear in-Pile Test Loop (open access)

The Brookhaven Chemonuclear in-Pile Test Loop

Technical report outlining the plan to develop the Brookhaven chemonuclear in-pile test loop because the interest in utilizing reactor radiation energy (fission-fragment recoil and neutron-gamma) for production of chemicals has developed to the point where a loop to study chemonuclear system in a reactor under dynamic conditions is necessary.
Date: April 23, 1962
Creator: Tucker, Walter D.; Waide, C.; Bezler, P. & Steinberg, Meyer, 1924-
System: The UNT Digital Library
Co60 Vitamin B12 Binding Capacity of Human Leukocytes (open access)

Co60 Vitamin B12 Binding Capacity of Human Leukocytes

This report examines the "vitamin B12 binding capacity of leukocytes obtained from three normal subjects and 19 persons with various hematologic disorders."
Date: April 23, 1962
Creator: Myer, Lee M.; Cronkite, Eugene P.; Miller, Inez F.; Mulsac, Claire W. & Jones, Irving
System: The UNT Digital Library
Cobalt (II) Halides as Electrolytes in Acentonitrile (open access)

Cobalt (II) Halides as Electrolytes in Acentonitrile

"The electrical conductance of CoCl2 and CoBr2 from 10−4 to 10−1 mol/l over the temperature range 0–35°C is reported. The effects of water as trace impurity, and the halide common ion effect on conductance are examined. The properties of these solutes are also examined using spectrophotometry and transport numbers. Crystalline “solvated” compounds, of empirical formulae [CoX2(CH3CN)3]x can be separated from the saturated solutions. The magnetic susceptibilities of the crystalline substrates are in accord octahedral and tetrahedral symmetry for the cationic and anionic species in these “solvates”, the bonding in both being the spin-free type for divalent cobalt. From the optical properties of the solutions it is apparent that the “anomalous” properties of these electrolytes can be understood in a series of simultaneous processes under Mass-Law control, in which CoX2, CoX42−, Co(CH3CN)62+ and [Co(CH3CN) 62+CoX42−]° are predominant."
Date: April 1962
Creator: Janz, George J.; Marcinkowsky, Arthur E. & Venkatasetty, H. V.
System: The UNT Digital Library
Comparative Cost Study of Processing Stainless Steel-Jacketed UO2 Fuel: Mechanical Shear-Leach vs Sulfex-Core Dissolution (open access)

Comparative Cost Study of Processing Stainless Steel-Jacketed UO2 Fuel: Mechanical Shear-Leach vs Sulfex-Core Dissolution

Comparison of the economics of mechanical shear-leach and Sulfex decladding-core dissolution head end treatments for processing typical tubular bundles of stainless steel-jacketed UO2 nuclear fuels.
Date: April 23, 1962
Creator: Adams, J. B.; Benis, A. M. & Watson, C. D.
System: The UNT Digital Library
Corrosion of thorium and uranium during long-term storage (open access)

Corrosion of thorium and uranium during long-term storage

From introduction: "The over-all objective of the present study was to determine the nature and extent of the present study was to determine the nature and extent of the corrosion of these materials under a variety of such storage conditions and to determine the ability of several potential protective coatings to retard this corrosion."
Date: April 10, 1962
Creator: Stephan, Elmer F.; Miller, P. D. & Fink, Frederick W.
System: The UNT Digital Library
Corrosion of Zircaloy in Crevices under Nucleate Boiling Conditions (open access)

Corrosion of Zircaloy in Crevices under Nucleate Boiling Conditions

Abstract: The MSAR corrosion test loop was used to study the effect of VKE-shaped crevices on the corrosion resistance of Zircaloy under boiling heat-transfer condtions in both ammoniated and lithiated water at pH 10.5.
Date: April 1962
Creator: Anderson, W. Kermit & McGoff, M. J.
System: The UNT Digital Library
Crystal Structure Of B 'Cu0.75Al0.25 (open access)

Crystal Structure Of B 'Cu0.75Al0.25

The problem of crystal structure of the martensitic B1 phase of the eutectic alloy in the Cu-Al system still requires a more accurate clarification (Hun ger and Dienst 1960, Tarora 1949). Martensitic phases in general are formed through small thrust (shear) deformations of the original lattice. On this basis the results of Hunger and Dienst (1960) are doubtful, since the lattice constants found by them have required a considerable reclassification. From the known lattice constants of the B1 phase (Tarora, 1949) and the orientation relationships of the B1 phase (Wassermann, 1934) one has expected a hexagonal lattice for the martensitic phase with [formula].
Date: April 20, 1962
Creator: Thomas, G. & Huffstutler, M.C., Jr.
System: The UNT Digital Library
Depression of Heme Formation and Theproduction of Free Porphyrin in Duck Erythrocytes (open access)

Depression of Heme Formation and Theproduction of Free Porphyrin in Duck Erythrocytes

From abstract: "The effects of a number of substances that depress protoheme formation and affect free protoporphyrin production in duck erythrocytes in vitro were measured."
Date: April 23, 1962
Creator: Klein, J. Raymond
System: The UNT Digital Library
Effect of Exposure Site on Weather Resistance of Porcelain Enamels Exposed for Three Years (open access)

Effect of Exposure Site on Weather Resistance of Porcelain Enamels Exposed for Three Years

From Introduction: "The present report describes the condition of all of the porcelain enamels after exposure for 3 yr."
Date: April 10, 1962
Creator: Moore, Dwight G. & Potter, Alan
System: The UNT Digital Library
Equations for Bilateral Heat Transfer to Fluids Flowing in Concentric Annuli (open access)

Equations for Bilateral Heat Transfer to Fluids Flowing in Concentric Annuli

Abstract: "Theoretical equations have been derived for calculating heat transfer coefficients for fluids flowing through concentric annuli for the following two cases: (A) constant and equal heat fluxes from both walls, and (B) constant, but unequal, heat fluxes from the walls, with equal wall temperatures at a given axial position along annular channel. In the derivations, the conditions of fully-established flow, and independence of physical properties with temperature variation across the flow channel, were assumed. The only geometrical parameter in this general case is the radius ratio r2/r1, and in the study it was varied from 1.0 to 10.0."
Date: April 10, 1962
Creator: Dwyer, Orrington Embry, 1912-
System: The UNT Digital Library
An Evaluation of Four Processes for Recovering Uranium from Zirconium Fuels at the Idaho Chemical Processing Plant (open access)

An Evaluation of Four Processes for Recovering Uranium from Zirconium Fuels at the Idaho Chemical Processing Plant

Report evaluating the technical and economic feasibility of four zirconium fuel processes: the present STR process, the modified Zirflex process, the barium fluozirconate process, and the sodium formate process.
Date: April 27, 1962
Creator: Burn, P.
System: The UNT Digital Library
Experimental Fast Ceramic Reactor Design Status Report as of October 31, 1961 (open access)

Experimental Fast Ceramic Reactor Design Status Report as of October 31, 1961

The design status of the Experimental Fast Ceramic Reactor (EFCR) is described for the period up to October 31, 1961. The primary purpose of the facility is to study the dynamic behavior of a fast ceramic reactor, including the experimental demonstration of the effectiveness of the Doppler coefficient in limiting the power excursion following a rapid insertion of reactivity.
Date: April 24, 1962
Creator: Horst, K. M.
System: The UNT Digital Library
The FAIM Code: a Multigroup, One-Dimensional Diffusion Equation Code (open access)

The FAIM Code: a Multigroup, One-Dimensional Diffusion Equation Code

Abstract: FAIM is a general multigroup, one-dimensional diffusion equation code programmed in FORTRAN language for the IBM 7090 computer.
Date: April 15, 1962
Creator: Baller, D. C.
System: The UNT Digital Library
Fire Tests of Precast Cellular Concrete Floors and Roofs (open access)

Fire Tests of Precast Cellular Concrete Floors and Roofs

From Abstract: "The results of an investigation of lightweight, precast cellular concrete planks are given. Fire tests were made of two floor and five roof specimens made up of these planks. Variables, included density of the cellular concrete, thickness and span of the planks, reinforcement, and cover for the latter."
Date: April 12, 1962
Creator: Ryan, J. V. & Bender, E. W.
System: The UNT Digital Library
Formation Constants of the Complex Species Formed by Interaction of Rare-Earth Nitrilotriacetate Complexes with an Equivalent Amount of Base (open access)

Formation Constants of the Complex Species Formed by Interaction of Rare-Earth Nitrilotriacetate Complexes with an Equivalent Amount of Base

From abstract: "The formation constants of the RChOH- species, formed by interaction of individual rare-earth nitrilotriacetate species and KOH at 25°C and an ionic strength of 0.1, have been determined by the potentiometric method, i.e., computed from the pH values of equilibrium mixtures containing varying proportions of rare-earth complex and base. The relationship of these constants to the ion-exchange separation of rare earths at high pH has been discussed."
Date: April 13, 1962
Creator: Guptak, Asim K. & Powell, Jack E.
System: The UNT Digital Library
Fuel Cycle Program - A Boiling Water Reactor Research and Development Program: Seventh Quarterly Progress Report January 1962 - March 1962 (open access)

Fuel Cycle Program - A Boiling Water Reactor Research and Development Program: Seventh Quarterly Progress Report January 1962 - March 1962

The Fuel Cycle Program is an integrated program of investigation in the Vallecitos Boiling Water Reactor and other facilities to improve the technological limits of boiling water reactors in several areas. Progress is reported here.
Date: April 30, 1962
Creator: Hodde, J. A.
System: The UNT Digital Library