Heat Exchanger Design Charts (open access)

Heat Exchanger Design Charts

From introduction: "The ORNL-ANP liquid-to-liquid heat exchanger design and development effort has been based on an exceptionally high performance matrix of closely-spaced small diameter tubes that permits practically pure counter-flow operation. In the course of full-scale aircraft power plant design work a number of charts for this type of heat exchanger has been prepared. These charts were intended in part to show the effects of the various parameters in a readily understandable form, and in part to simplify and to reduce markedly the chore of making detailed design calculations. These charts have proved so helpful it seemed very worthwhile to assemble them into a report along with brief explanations and sample calculations."
Date: December 7, 1952
Creator: Fraas, A. P. & LaVerne, M. E.
System: The UNT Digital Library
A Preliminary Survey of Radioactive Constituents in Rainwater at ORNL (open access)

A Preliminary Survey of Radioactive Constituents in Rainwater at ORNL

Technical report surveying radio-chemical analyses by ORNL's Analytical Chemistry Division and Health-Physics Division of large volumes of rainwater for plutonium, uranium, and fission products. Overall, carrying efficiencies for Al(OH)3 scavenging of rainwater were determined for these elements, as well as for Pu and U. [From Abstract, Introduction]
Date: December 4, 1950
Creator: Booksbank, W. A., Jr.; Emmons, A. H.; Gost, J. W. & Reynolds, S. A.
System: The UNT Digital Library
The Corrosion of Miniature Fuel Plates in Simulated Reactor Cooling Water (open access)

The Corrosion of Miniature Fuel Plates in Simulated Reactor Cooling Water

Technical report issued as one of a series of reports concerned with corrosion studies for the Materials Resting Reactor, created to both determine the effect of various practices for fuel plate fabrication on corrosion resistance and to determine the extent of penetration of the fuel plates by localized corrosion attack. [From Introduction]
Date: December 18, 1950
Creator: English, James L.
System: The UNT Digital Library
Plate Efficiency in the Exchange of Deuterium Between Ammonia and Hydrogen (open access)

Plate Efficiency in the Exchange of Deuterium Between Ammonia and Hydrogen

Technical report outlining measurements of the equilibrium in the exchange of deuterium between ammonia and hydrogen and of the kinetics of this reaction. Details a series of tests carried out to measure Murphree plate efficiencies.
Date: December 3, 1951
Creator: Perlman, Morris L. & Bigeleisen, Jacob
System: The UNT Digital Library
The Concentration of Deuterium by Chemical Exchange Between Hydrogen and Ammonia (open access)

The Concentration of Deuterium by Chemical Exchange Between Hydrogen and Ammonia

Technical report describing the results of the chemical reaction between potassium amide and liquid ammonia and the exchange of hydrogen between hydrogen gas and liquid ammonia. This report finds that the reactions may be sufficiently rapid to be useful for isotope separations on a larger scale.
Date: December 15, 1951
Creator: Perlman, M. L. & Bigeleisen, J.
System: The UNT Digital Library
Reactor Operations Division Monthly Report; December 1951 (open access)

Reactor Operations Division Monthly Report; December 1951

Technical report analyzing the down time of the Brookhaven National Laboratory nuclear reactor and resulting changes in reactivity.
Date: December 1951
Creator: Powell, R. W.
System: The UNT Digital Library
Evaluation of Tributyl Phosphate in Jet Mixing Columns as a Solvent for Uranium Extraction From Slurry-Type Ore Feeds (open access)

Evaluation of Tributyl Phosphate in Jet Mixing Columns as a Solvent for Uranium Extraction From Slurry-Type Ore Feeds

Technical report outlining the physical operability of 30% tributyl phosphate in a hydrocarbon dilutent for the extraction of uranium from more feed slurries. Operability had been satisfactorily demonstrated in jet mixing columns at the pilot plant of the Mallinckrodt Chemical Works. [From Abstract]
Date: December 7, 1950
Creator: Runion, T. C. & Yeager, J. H.
System: The UNT Digital Library
Boiling Reactors: A Preliminary Investigation (open access)

Boiling Reactors: A Preliminary Investigation

Technical report detailing kinetic equations that have been developed for a boiling-type reactor and inherent reactor stability studies that have been made on the basis of these equations. Presents features of the proposed reactor, comparisons of circulating types, investigations of bubble-rise velocities, effects of transient conditions of vapor mass in steam chest, and bubble time delay functions yield favorable results. [From Abstract]
Date: December 12, 1951
Creator: Stein, J. M. & Kasten, P. R.
System: The UNT Digital Library
Thorium and Thorium Alloys Preliminary Corrosion Tests (open access)

Thorium and Thorium Alloys Preliminary Corrosion Tests

Technical report investigating the corrosion resistance of thorium and thorium alloys containing from 2 to 6% chromium, columbinium (niobium), titanium, zirconium and titanium-zirconium in distilled water at 95ºC. The true effects of the various alloy additions could not be determined because of the more marked effect of cold working. [From Abstract]
Date: December 19, 1951
Creator: Olsen, Arnold R.
System: The UNT Digital Library
The Hydrolysis of Tributyl Phosphate Ad Its Effect on the Purex Process (open access)

The Hydrolysis of Tributyl Phosphate Ad Its Effect on the Purex Process

From abstract: "The rate of hydrolysis of TBP and the effect of the hydrolysis products in the Purex Process have been studied. Hydrolytic conditions may be encountered in the process which would lead to formation of dibutyl phosphoric acid, causing significant losses of tetravalent plutonium in stripping. This situation may be easily alleviated by reducing and stripping the plutonium in the trivalent state."
Date: December 13, 1951
Creator: Reilly, V. J. & Lanham, W. B.
System: The UNT Digital Library
Enrichment of Uranium 236 (open access)

Enrichment of Uranium 236

From abstract: "Neutron-irradiated uranium was electromagnetically separated to provide enrichment of the isotope of mass 236. The final isotopic abundance of U 236 was determined to be 95% in 1800 milligrams of uranium. Useful by-products of the program were 22 grams of 25% U 236 and 1100 grams of 99.7% U 235. These enriched materials have been made available for use on Atomic Energy Commission projects. Possible application of this separation process to recovery of the fuel from the MTR reactor is described."
Date: December 1951
Creator: Harmatz, B.; McCurdy, H. C.; Case, F. N. & Livingston, R. S.
System: The UNT Digital Library
Enrichment of Uranium 236 (open access)

Enrichment of Uranium 236

From abstract: "Neutron-irradiated uranium was electromagnetically separated to provide enrichment of the isotope of mass 236. The final isotopic abundance of U 236 was determined to be 95% in 1800 milligrams of uranium. Useful by-products of the program were 22 grams of 25% U 236 and 1100 grams of 99.7% U 235. These enriched materials have been made available for use on Atomic Energy Commission projects. Possible application of this separation process to recovery of the fuel from the MTR reactor is described."
Date: December 1951
Creator: Harmatz, B.; McCurdy, H. C.; Case, F. N. & Livingston, R. S.
System: The UNT Digital Library
Measurement of the Behavior of a Plasma in a Magnetic Field by Means of Probes (open access)

Measurement of the Behavior of a Plasma in a Magnetic Field by Means of Probes

Abstract: "Probes were used to measure certain properties of the cloud of positive ions and electrons ejected from a pulsed ion source having two hydrogen-loaded electrodes. Time-of-flight measurements show: the presence of H+ ions with 50 ev directed energy; an increase of this energy with increasing pulse current in the source; a higher peak yield of ions with higher peak currents in the source; and higher yields and higher ion energies up to 110 ev have been recorded with the use of a pulsed magnetic field impressed upon the source. The neutral positive ion-electron beam from the source has been projected against an increasing magnetic field and the reflected and transmitted signals have been recorded and compared as a function of the magnetic field. Probe signals from the plasma as it encounters the magnetic field are oscillatory, suggesting that magnetohydrodynamic phenomena are presented."
Date: December 1, 1954
Creator: Bostick, W. H.; Zizzo, S. G. & Cook, Buford
System: The UNT Digital Library
Use of Thermal Electromotive Forces to Product Magnetic Field in a Controlled Thermonuclear Reactor (open access)

Use of Thermal Electromotive Forces to Product Magnetic Field in a Controlled Thermonuclear Reactor

The following report investigates the possible use of thermal emf's to produce the plasma-containing magnetic field in a thermonuclear reactor.
Date: December 27, 1954
Creator: Northrop, Theodore G.
System: The UNT Digital Library
An Exact Analysis of Limited Plane Plasma in a Magnetic Field (open access)

An Exact Analysis of Limited Plane Plasma in a Magnetic Field

Introduction: "Prior analyses of a plasma in a magnetic field have been limited, as far as the writer is aware, to cases in which the relative change in field over the orbital distance and the relative change in ion concentration are both small, or in which the relations have been viewed in a purely hydrodynamical way. The first approach excludes cases which can be of considerable interests, for it fails near a plasma edge. The second loses all sight of the structure imposed by the orbital motions."
Date: December 2, 1954
Creator: Tonks, Lewi, 1897-1971
System: The UNT Digital Library
Chemical Development, Quarterly Progress Report, July-September, 1953. (open access)

Chemical Development, Quarterly Progress Report, July-September, 1953.

Introduction: "During the last quarter, members of the Chemical Development Group have been concerned with six major projects. (1) thermal and radiation properties of organic materials as moderators and coolants, (2) thermal and radiation stability of mirconium hydride, (e) reactor accessibility (transport of radioactive materials in cooling systems, ................. There have been, in addition, a number of smaller service projects, mostly of an analytical nature.:
Date: December 7, 1953
Creator: Loftness, R. L.
System: The UNT Digital Library
General Chemistry, Quarterly Progress Report, April-June 1954 (open access)

General Chemistry, Quarterly Progress Report, April-June 1954

"General Chemistry investigations reported herein includes: (1) the Organic Coolant-Moderator Program, (2) investigations on zirconium hydride, and (3) analytical chemistry."
Date: December 15, 1954
Creator: Colichman, Eugene L.
System: The UNT Digital Library
Melting Point -- Composition Diagrams in the U-UBr3 System (open access)

Melting Point -- Composition Diagrams in the U-UBr3 System

Abstract. A portion of the liquid-solid phase equilibrium region of the system U-UBr3 has been investigated by the method of thermal analysis. Uranium tribromide was prepared by introducing bromine vapor into a bulb containing finely divided uranium formed from the hydride. Cooling curves were obtained with tribromide and then with various compositions of tribromide and uranium. the information obtained showed that no solid sub halide exists but that the metal was soluble in the halide.
Date: December 20, 1944
Creator: Thurmond, Carl
System: The UNT Digital Library
Crystal Densities of Uranium Chlorides (open access)

Crystal Densities of Uranium Chlorides

Abstract: "Using xylene as the densimetric solvent, the crystal densities have been determined by the pyknometric method for the following chlorides, UCl3, UCl4, UCl6(UCl4), UCl6 and U02Cl2."
Date: December 13, 1946
Creator: Sterett, C. C. & Calkins, V. P.
System: The UNT Digital Library
TO₃ Reduction and Chlorination in the Experimental Glass Fluidizer (open access)

TO₃ Reduction and Chlorination in the Experimental Glass Fluidizer

Abstract: "Temperatures above 400 C are required before reduction will take place with AH3. Above 500 C, a pyrophoric product was obtained. The chlorination temperature should be about 350 C initially and above 450 C at the end of the reaction to achieve 99% chlorination."
Date: December 20, 1945
Creator: Lowrie, Robert Sydney & Hubbard, J. V.
System: The UNT Digital Library
Homogeneous Reactor Preliminary Process Design Report (open access)

Homogeneous Reactor Preliminary Process Design Report

"The following report is meant to serve a two fold purpose. First, it is the quarterly report of the homogeneous reactor project for the Technical Division of Oak Ridge National Laboratory. Secondly, it is a description and general feasibility discussion of a 200-1000 K.W. pilot model, homogeneous reactor."
Date: December 28, 1949
Creator: Graham, C. B.; Secoy, C. H.; Spiewak, Irving; Taylor, E. H.; Weinberg, Alvin Martin, 1915-2006; Winters, C. E. et al.
System: The UNT Digital Library
Measurements of an Iron and Borated Water Shield in the Lid Tank : Experiment 10 (open access)

Measurements of an Iron and Borated Water Shield in the Lid Tank : Experiment 10

The following report measures a shield mockup in three regions: the first made almost entire of iron; the second, transition, region is made of various thicknesses of B4C; and the third region was borated water. The iron samples used in the experiments were made in the form of rectangular plates and place in the lid tank; however, the plates were not completely flat and created a water gap that was measured in this report.
Date: December 14, 1950
Creator: Blizard, E. P. & Clifford, C. E.
System: The UNT Digital Library
Progress Report for the Month of December, 1947 : Contract No. W-38-094-eng-27 (open access)

Progress Report for the Month of December, 1947 : Contract No. W-38-094-eng-27

This report for December, 1947 describes progress in ore dressing and pyrometallurgical studies, chemical work on phosphates, and analytical work.
Date: December 31, 1947
Creator: Center, E. J.; Pray, H. A.; Richardson, A. C. & Sullivan, John D.
System: The UNT Digital Library
Supplement to Document HW-21374 -- Multiplication Constants for Hanford Type Lattices: Graphite of Variable Density (open access)

Supplement to Document HW-21374 -- Multiplication Constants for Hanford Type Lattices: Graphite of Variable Density

Report discussing "the effect on the multiplication constant of using graphite of various density." Results are tabulated and plotted.
Date: December 28, 1951
Creator: Dahlberg, Richard C.
System: The UNT Digital Library