An Automatic Analyzing Monitor for Reactor Effluent Cooling Water (open access)

An Automatic Analyzing Monitor for Reactor Effluent Cooling Water

From objective: "The objective of this work was to design, develop, assemble, and test and automatic analyzing monitor for recording the prominent isotopes in reactor effluent cooling water."
Date: May 1, 1959
Creator: Rieck, H. G.; Ratcliffe, C. A. & Schwendiman, L. C.
System: The UNT Digital Library
Autunite From Mt. Spokane, Washington (open access)

Autunite From Mt. Spokane, Washington

Report discussing the coarsely crystalline autunite in granitic rock near Mt. Spokane, Washington. "This report is an abstract of a paper with the same title that is planned for publication in the American Mineralogist."
Date: May 1959
Creator: Leo, G. W.
System: The UNT Digital Library
Euorochemic Assistance: Chemical Technology Division Unit Operations Section Monthly Progress Report, November, 1958. (Sections 1.0, 5.0, 6.0, 8.0 of ORNL CF-58-11-93) (open access)

Euorochemic Assistance: Chemical Technology Division Unit Operations Section Monthly Progress Report, November, 1958. (Sections 1.0, 5.0, 6.0, 8.0 of ORNL CF-58-11-93)

To better understand the solvent extraction process much effort has been and is being expended at ORNL and elsewhere to measure reaction kinetics of the extraction reactions. To date these efforts have been largely unsuccessful, due to the attempt to apply homogeneous reaction kinetics to two-phase systems. An optical method has been devised for analyzing the concentration profile in the vicinity of a quiescent interface during steady-state diffusion at rather large molecular fluxes. The system under study is the extraction of uranyl ion from water by a TBP solution. Considerable effort has been directed to eliminating leaks in the diffusion cell and testing the optical system/
Date: May 1, 1959
Creator: Shank, E. M.
System: The UNT Digital Library
Eurochemic Assistance: Chemical Technology Division Unit Operations Section Progress Report, December, 1958. (Sections 5.0, 6.0, 8.0) (open access)

Eurochemic Assistance: Chemical Technology Division Unit Operations Section Progress Report, December, 1958. (Sections 5.0, 6.0, 8.0)

In order to make rational predictions of the operating characteristics of uranium anion exchange contactors, an understanding of the mechanism and kinetics of the exchange is necessary. Toward this objective an effort is being made to determine the equilibrium sorption isotherms and rates of sorption of uranium on the anion exchange resin Dovex 21K.
Date: May 1, 1959
Creator: Shank, E. M.
System: The UNT Digital Library
Eurochemic Assistance: Monthly Progress Report for Chemical Development Section B, January, 1959 (Sections 1.0, except 1.42, and 2.0) (open access)

Eurochemic Assistance: Monthly Progress Report for Chemical Development Section B, January, 1959 (Sections 1.0, except 1.42, and 2.0)

In order to make rational predictions of the operating characteristics of uranium anion exchange contactors, an understanding of the mechanism and kinetics of the exchange is necessary. Toward this objective an effort is being made to determine the equilibrium sorption isotherms and rates of sorption of uranium on the anion exchange resin Dovex 21K.
Date: May 1, 1959
Creator: Shank, E. M.
System: The UNT Digital Library
An Experimental Evaluation of the Radiation Protection Afforded by a Large Modern Concrete Office Building (open access)

An Experimental Evaluation of the Radiation Protection Afforded by a Large Modern Concrete Office Building

Abstract: "An experimental study was made to determine the effective shielding provided by a modern reinforced-concrete office building (AEC Headquarters building) from nuclear fallout. Pocket ionization chambers were used for measurement of the radiation-field strength. Fallout was simulated with distributed and point-source configurations of Co-60 and Ir-192 sources. Four typical sections were selected for study, and experiments were performed on each. These included an external wing with exposed basement walls and an external wing with a buried basement. Roof studies were made on an internal wing with a full basement and on the east end of wing A, which has a thin-roof construction. The thick-roof construction of 8 in. of concrete and 2 in. of rigid insulation covers all the building except the east end of wing A, which has 4 in. of concrete and 2 in. of insulation."
Date: May 1, 1959
Creator: Batter, J. F., Jr.; Kaplan, A. L. & Clarke, Eric Thacher
System: The UNT Digital Library
Experimental Gas-Cooled Reactor: Preliminary Hazards Summary Report (open access)

Experimental Gas-Cooled Reactor: Preliminary Hazards Summary Report

From introduction: This report describes progress during the first quarter on all phases of the ANPP Code Development Program, Pressurized Water Task. The objective of this program is the development of a nuclear physical model and its calculation code for pressurized-water-cooled and moderated reactors to predict accurately reactivity, rod positions, and power distributions at operating temperatures, and reactor life from a nuclear standpoint.
Date: May 1959
Creator: unknown
System: The UNT Digital Library
Handbook: A Technique for Preparing Desert Terrain Analogs (open access)

Handbook: A Technique for Preparing Desert Terrain Analogs

"A technique is described whereby desert areas selected for terrain comparison are mapped in terms of general terrain factors, geometry factors, ground factors, and vegetation" (p. vii).
Date: May 1959
Creator: Van Lopik, Jack R. & Kolb, Charles R.
System: The UNT Digital Library
Nitrous Acid Behavior in Purex Systems (open access)

Nitrous Acid Behavior in Purex Systems

In HAPO solvent extraction processes there are two independent aspects of nitrous acid chemistry. One concern the decomposition of the solvent through nitration reactions and the attendant problems. These reactions are autocatalytic in the presence of nitric acid and have threshold values for both temperature and nitric acid concentration for a given solvent below which nitrous acid disappears and above which it is generated with continuous destruction of the solvent. These reactions are identical to those found in the prior study of the hexone system.
Date: May 1, 1959
Creator: Burger, L. L. & Money, M. D.
System: The UNT Digital Library
Positional Tolerancing at Sandia Corporation (open access)

Positional Tolerancing at Sandia Corporation

Abstract: "This brochure presents a brief introduction to the Positional Tolerance Method of DImensioning as employed by Sandia Corporation. The emphasis is placed on the elimination of ambiguities and increase in tolerances provided by this method as compared to the older, bilateral method."
Date: May 1959
Creator: Sandia Corporation. Design Definition Department.
System: The UNT Digital Library
Preliminary report on radioactive mineral deposits in the Gulf Coastal Plain of Texas and Louisiana, north and east of the Guadalupe River (open access)

Preliminary report on radioactive mineral deposits in the Gulf Coastal Plain of Texas and Louisiana, north and east of the Guadalupe River

"Approximately 30 radioactive mineral deposits are known to occur in the Gulf Coastal Plain of Texas and Louisianna, north and east of the Guadalupe River. A preliminary field examination and sampling of each deposit has been made"
Date: May 1959
Creator: Blair, Robert G.
System: The UNT Digital Library
Progress Report No. 54 for the Period through April 30, 1959 (open access)

Progress Report No. 54 for the Period through April 30, 1959

This is the fifty-fourth progress report of the Laboratory for Nuclear Science at the Massachusetts Institute of Technology. Progress reported covers the period for Physics and Chemistry through April 30,1959. Progress is reported on: (1) Chemistry of the fission elements group, (2) Nuclear chemistry (inorganic) group, (3) Nuclear chemistry (organic) group, (4) Cosmic ray group, (5) High energy accelerator physics group, (6) Bubble chamber group, (7) Liner acceleratory group, (8) Rockefeller generator group, (9) ONR generator group, (8) Radioactivity group, (9) Cyclotron group, (10) Theoretical group, (11) Personnel listing.
Date: May 1, 1959
Creator: unknown
System: The UNT Digital Library
Remote Radiological Monitoring (open access)

Remote Radiological Monitoring

From abstract: A gamma-radiation telemetering system was utilized by Civil Effects Test Group personnel to measure fallout levels at the Nevada Test Site from the vicinity of Ground Zero out to, and including, an area bounded by Reno, Nevada; Salt Lake City, Utah; Kingman, Arizona; and Barstow, California.
Date: May 1, 1959
Creator: Sigoloff, Sanford C. & Borella, H. M.
System: The UNT Digital Library
Report of the Sodium Heavy-Water Reactor Task Force: May 1959 (open access)

Report of the Sodium Heavy-Water Reactor Task Force: May 1959

"The sodium-heavy-water reactor concept was evaluated on the basis of (1) its technical feasibility and (2) its potential for the economical production of electric power."
Date: May 1959
Creator: unknown
System: The UNT Digital Library
Review of Soils Design, Construction, and Performance Observations: Lookout Point Dam, Oregon (open access)

Review of Soils Design, Construction, and Performance Observations: Lookout Point Dam, Oregon

This report reviews the performance of the Lookout Point Dam located on the Middle Fork of the Willamette River in Oregon. "This study is one of a series of similar studies of the foundation and soil mechanics features of earth dams [...] In these studies original design data are reviewed, construction experience is summarized, and performance fo the completed structures is compared with design predictions to provide information for use in the design and construction of future similar projects" (p. 1).
Date: May 1959
Creator: Waterways Experiment Station (U.S.)
System: The UNT Digital Library
The Scattering of Thermal Radiation Into Open Underground Shelters (open access)

The Scattering of Thermal Radiation Into Open Underground Shelters

From Introduction: "The elimination of the burn hazard in shelters depends upon a separate, systematic investigation of each suspected agent. The purpose of the present investigation was to evaluate the contribution made by radiant energy and, if such contribution proved to be significant, to suggest means of eliminating this component."
Date: May 1959
Creator: Davis, T. P.; Miller, N. D.; Ely, T. S.; Basso, J. A. & Pearse, H. E.
System: The UNT Digital Library
Thermodynamic Properties of Dilute Aqueous Hydrochloric Acid Solutions at Elevated Temperatures from Electromotive Force Measurements (open access)

Thermodynamic Properties of Dilute Aqueous Hydrochloric Acid Solutions at Elevated Temperatures from Electromotive Force Measurements

A study of the thermodynamic properties of dilute aqueous hydrochloric acid solutions at elevated temperatures by an electromotive force method was undertaken for several reasons. First, a great need for fundamental information at elevated temperatures was evident from the growing number of industries making use of aqueous solutions at elevated temperatures. Second, the use of the hydrogen electrode against the silver-silver chloride electrode in dilute hydrochloric acid solutions promised to give fundamental thermodynamic information on an important electrode system as well as on hydrochloric acid over a wide temperature range.
Date: May 1959
Creator: Greeley, Richard Stiles
System: The UNT Digital Library
Eurochemic Assistance Program: Status Report as of April 1, 1959 (open access)

Eurochemic Assistance Program: Status Report as of April 1, 1959

Considerable delay has occurred in getting ratification of the Eurochemic charter by 80% of the participating nations. The French, who were not expected to ratify the charter until an elected government was again established , actually ratified under de Gaulle late in 1958.
Date: May 5, 1959
Creator: Nicholson, E. L.
System: The UNT Digital Library
Eurochemic Information Exchange- Answers to Specific Questions (open access)

Eurochemic Information Exchange- Answers to Specific Questions

A number of the questions which have been posed to us in the subject references are commented upon below. These have been reviewed by personanel of the Research and Engineering Operation and the Facilities Engineering Operation, Chemical Processing Department, and of the Chemical Research and Development Operation, Hanford Laboratories Operation. Particular acknowledment is given G. J Alkire, J. P. Duckworth, J. B. Fecht, R. G. Geier, E. R. Irish, H. M. Jones, G. C. Oberg, A. M. Platt, W. H. Reas, W. C. Schmidt, R. J. Sloat, W. H. Swift, M. T. Walling and L. L. Zahn of these organizations for assistance given assembling this information.
Date: May 5, 1959
Creator: Hill, O. F.
System: The UNT Digital Library
Liquid Metal Fuel Reactor Experiment:  Dynamic Utility Test Loop (open access)

Liquid Metal Fuel Reactor Experiment: Dynamic Utility Test Loop

This report provides an overview of the creation of the Liquid Metal Fuel Reactor Experiment program. It furthers the work by constructing a single loop to test all the components required for the 16 loop reactor. This utility loop was also constructed to provide a facility for testing various components such as valves and flow meters.
Date: May 5, 1959
Creator: Baker, O. H.
System: The UNT Digital Library
Flame Photometric Determination of Iron Parts I, II, III and IV (open access)

Flame Photometric Determination of Iron Parts I, II, III and IV

A study was made of a method for the flame photometric determination of iron. In Part I of this report, the flame emission spectrum of iron, measured by means of a Beckman Model DU spectrophotometer with a flame attachment, is compated to that measured with an ORNL high-sensitivity, recording, single-beam instrument, in order to determine which instrument is best suited for this application. Although it was found that the Beckman product has the higher resolving power over the wavelength region of 360 to 400mu, it does no posses the sensitivity or ease of operation of the ORNL instrument. On this basis, the ORNL flame spectrophotometer is used in subsequent tests. After selecting the best-suited instrument for the flame photometric determination of iron, it was necessary to establish the optimum operating conditions for this particular method. These conditions are described in Part II.
Date: May 6, 1959
Creator: Menis, Oscar
System: The UNT Digital Library
Niobium Phase Diagrams : Manuscript Report on Niobium-Carbon System (open access)

Niobium Phase Diagrams : Manuscript Report on Niobium-Carbon System

Abstract: "The niobium-carbon system has been determined by X-ray and metallographic examination of sintered and arc-cast alloys. Two carbides exist: hexagonal Nb2C with a limited range of homogeneity, and cubic NbC with a solubility range from 8.25 to 10.25 weight per cent carbon. Dilute alloys freeze by eutectic reaction at 2230 C. The solubility of carbon in niobium is 0.80 at the eutectic temperature, but this decreases rapidly with temperature. Metallographic evidence indicates a peritectic reaction between melt, Nb2C, and NbC; alloys richer in carbon than NbC freeze by eutectic reaction."
Date: May 6, 1959
Creator: Elliott, Rodney P.
System: The UNT Digital Library
Critical Incident Alarm - Model I Instruction and Maintenance Manual (open access)

Critical Incident Alarm - Model I Instruction and Maintenance Manual

The HAPO Critical Incident Alarm, Model I, is an instrument designed to give an audible and visual alarm signal in the event of a critical incident to which it is exposed. There will be thirty-one (31) of these instruments installed and several spares located in the various manufacturing buildings in the Chemical Processing Department where there exists any possibility of a critical incident occurring. The instrument is intended as a post or after-the-fact warning device. It will offer no protection prior or leading up to, nor prevent, a critical incident. They are intended to be operated from the 115 V. A.C., 60 C.P.S. emergency line power. The instrument is self-contained, including the radiation detector, and will be calibrated to alarm at 500 mr/hour in a gamma field.
Date: May 8, 1959
Creator: Kelly, P. R.
System: The UNT Digital Library
Improvements in Water Treatment for Once-Through Reactor Cooling (open access)

Improvements in Water Treatment for Once-Through Reactor Cooling

Nearly all nuclear reactors being designed and built today- whether for research, power, or productions of fissionable materials- use recirculating fluids for cooling. However, a number of production reactors are still operating with single-pass cooling by treated natural water. The Hanford Atomic Products Operation of the General Electric Company presently operates production reactors for the AEC at Richland, Washington. The first reactors were built during World War II, and utilized a standard water treatment which was designed to provide large quantities of settled, filtered Columbia River water for once-through cooling.
Date: May 8, 1959
Creator: Richman, R. B.
System: The UNT Digital Library