The Ductility of Brazed Stainless Steel Joints (open access)

The Ductility of Brazed Stainless Steel Joints

Abstract: "The ductility of Type 310 stainless steel T-joints brazed with GE-62 brazing alloy was measured at room temperatures 1200, 1650, and 1800 F. The measure of ductility was taken as the plastic axial strain required to crack braze fillets in T-section tensile specimens. At elevated temperatures, the ductility of as-brazed joints approximated that of the stainless steel, but at room temperature the brazed joints had only one-tenth the ductility of the base metal. Annealing for 16 hr at 1800 F in air was found to triple the room-temperature ductility of the brazed joint."
Date: July 8, 1953
Creator: Saller, Henry A.; Stacy, J. T. & Eddy, N. S.
Object Type: Report
System: The UNT Digital Library
HASL Aerial Survey System (open access)

HASL Aerial Survey System

Radioactive debris from nuclear detonations may fall out over an extensive area. A rapid evaluation of the distribution of such surface contamination cam be obtained by an aircraft mounted detector. The gamma field measured in the aircraft can be related to the intensity on the ground. The HASL Top Hat'' system measures the radiation intensity, in an aircraft, at any altitude up to 1500 feet. The data are continuously compensated to the reading that would be obtained if the measurements were taken at three feet from thc ground surface. It will record the ground radiation field intensities from 0.01 mr/hr to 1000 r/hr. The Telepulse Coding Unit converts this information to a signal suitable for transmission to a plotting center via a standard voice radio transmitter. The transmitted signal is decoded by a Telepulse Receiving Unit and is automatically recorded on a strip chart. The radiation data must be correlated with the aircraft position to determine the location amd intensity distribution of the contaminated area.
Date: July 29, 1957
Creator: Cassidy, M. E.; Graveson, R. T. & LeVine, H. D.
Object Type: Report
System: The UNT Digital Library
Terminal Report on the Radiolanthanum Laboratory (open access)

Terminal Report on the Radiolanthanum Laboratory

"The purpose of this present document is twofold: (1) To acquaint the reader with the planning of the radiochemical laboratory designed for the analytical control of the Radio-lanthanum Process. (2) To define the terminal status of the design of this laboratory and its equipment."
Date: July 21, 1950
Creator: Figenshau, J. K.
Object Type: Report
System: The UNT Digital Library
Grain Refinement of the As-Cast Uranium-5 w/o Chromium Alloy by Ternary Additions (open access)

Grain Refinement of the As-Cast Uranium-5 w/o Chromium Alloy by Ternary Additions

Abstract: "Refinement of grain size of the base uranium-chromium eutectic alloy (uranium-5 w/o chromium) by ternary additions is discussed. Thirteen additions to the base alloy were investigated, and three additions were found to exhibit worthwhile grain-refinement tendencies. The three alloys, uranium-5 w/o chromium-0.2 w.o molybdenum, uranium-5 w/o chromium-0.2 w/o germanium, and uranium-5 w/o chromium-0.2 w/o niobium, were heat treated to produce final grain-size structures of between 0.015 and 0.033 mm."
Date: July 5, 1955
Creator: Saller, Henry A.; Dickerson, Ronald F.; Murr, William E. & Bauer, Arthur A.
Object Type: Report
System: The UNT Digital Library
Further Studies on Large-Batch Melting of Uranium (open access)

Further Studies on Large-Batch Melting of Uranium

The following report focuses on an investigation made to determine if vacuum melting was an absolutely necessary step in the metallurgical process of melting and casting uranium.
Date: July 11, 1955
Creator: Rengstorff, George W. & Lownie, Harold W., Jr.
Object Type: Report
System: The UNT Digital Library
A New Anionic Solvent Extraction Technique (open access)

A New Anionic Solvent Extraction Technique

From abstract: "The extraction of acids with long-chain amines is described. Preliminary results on the extraction of the amine salts of polonium, plutonium and uranium are given."
Date: July 17, 1952
Creator: Moore, F. L.; Kelley, M. T. & Susano, C. D.
Object Type: Report
System: The UNT Digital Library
The Effect of Gaps on Pile Reactivity (open access)

The Effect of Gaps on Pile Reactivity

From abstract: "The variation of the reactivity of a pile as a function of width of a transverse gap is obtained. The method involves first finding the boundary condition satisfied by the flux at the gap face. This, in principle, provides enough information for a complete solution of the pile equations. A method for calculating the reactivity change is presented. The calculated reactivity is compared with experiment and a brief discussion of the validity of the approximations is given."
Date: July 14, 1952
Creator: Tamor, S. & Ergen, W. K.
Object Type: Report
System: The UNT Digital Library
A Continuous Fission Product Separation Process; I. Removal of the Rare Earths (Lanthanum Cerium, Praseodymium, and Neodymium) From a Typical Liquid Bismuth-Uranium Reactor Fuel by Contact with Fused LiCl-KCl Mixtures (open access)

A Continuous Fission Product Separation Process; I. Removal of the Rare Earths (Lanthanum Cerium, Praseodymium, and Neodymium) From a Typical Liquid Bismuth-Uranium Reactor Fuel by Contact with Fused LiCl-KCl Mixtures

Technical report investigating the distribution of rare earth elements between a liquid bismuth-uranium solution and fused KCI-LiCi mixtures. Report warrants further research on the liquid bismuth-uranium-fused salt system due to the benefit of continuous fission removal processes.
Date: July 1, 1951
Creator: Bareis, D. W.
Object Type: Report
System: The UNT Digital Library
A Solvent Extraction Method for Neptunium (237) Analysis (open access)

A Solvent Extraction Method for Neptunium (237) Analysis

Technical report describing a rapid and quantitative radiochemical method for the analysis of neptunium (237). This method is based on the extraction of neptunium (IV) with thenoyl-trifluoracetone in xylene. Neptunium (237) is separated free from other alpha emitters and from non-radioactive interferences, and the method may be readily adapted to remote control. [From Abstract]
Date: July 10, 1951
Creator: Moore, Fletcher L.
Object Type: Report
System: The UNT Digital Library
Shielding Reactor Corrosion Studies (open access)

Shielding Reactor Corrosion Studies

Technical report outlining the investigation of corrosion on MTR type fuel elements for the Shielding Reactor in filtered water. Report includes two basic types of protection: element pretreatment by either anodizing or alodizing, and solution control using nitric acid to maintain a pH of 5.5 to 6.5 or the addition of 60 ppm sodium chromate as an inhibitor. [From Abstract]
Date: July 9, 1951
Creator: Olsen, Arnold R.
Object Type: Report
System: The UNT Digital Library
Analysis of Bulk Shielding Facility Neutron Dosimeter Data (open access)

Analysis of Bulk Shielding Facility Neutron Dosimeter Data

Technical report calculating "effective removal cross sections" for Pb, Fe and O from measurements of fast neutron does in the water surrounding the BSF reactor. The values for Pb and Fe agree quite well with those previously determined from Lid tank data, whereas that for O is somewhat lower. [From Abstract]
Date: July 17, 1952
Creator: Podgor, S.
Object Type: Report
System: The UNT Digital Library
Physics Division Quarterly Progress Report for Period Ending March 20, 1951 (open access)

Physics Division Quarterly Progress Report for Period Ending March 20, 1951

Technical report covering classified work of the Critical Experiments Program in the Physics Division for the period December 20, 1950 to March 20, 1951. Report outlines investigations of properties of critical assemblies composed of uranium and various reflectors and moderators, preliminary measurements of the effective energy for fission in the assembly. [From Introduction and Summary]
Date: July 2, 1951
Creator: Bernstein, S.; Snell, A. H. & Wollan, E. O.
Object Type: Report
System: The UNT Digital Library
Some Preliminary Investigations in the Use of a Supersonic Mercury Vapor Jet for Providing an Energetic Neutral Beam (open access)

Some Preliminary Investigations in the Use of a Supersonic Mercury Vapor Jet for Providing an Energetic Neutral Beam

Report discussing experiments conducted under the Livermore "Waldo" project to determine "(1) surface densities attainable in a supersonic mercury vapor jet stream, (2) the approximate efficiency of a mercury jet for neutralizing a proton beam, and (3) the mercury partial pressure contribution in the bore due to side streaming from the mercury jet."
Date: July 18, 1956
Creator: Steinhaus, J. F.
Object Type: Report
System: The UNT Digital Library
20,000 KW Nuclear Power Plant Study for United States Atomic Energy Commission (open access)

20,000 KW Nuclear Power Plant Study for United States Atomic Energy Commission

Introduction: In September of 156, Gilbert Associates, Inc., entered into a contract with the United States of America, acting through the United States Atomic Energy Commission, for the study and preliminary design of a nuclear power plant being considered for integration into a central station power system at an overseas site.
Date: July 7, 1957
Creator: Gilbert Associates, Inc.
Object Type: Report
System: The UNT Digital Library
Reconnaissance of Red Rock Valley, Apache County, Arizona (open access)

Reconnaissance of Red Rock Valley, Apache County, Arizona

Abstract: Reconnaissance of Red Rock Valley was begun on December 10, 1953, and completed on February 11, 1954. The mines in the region were investigated and all exposures of Salt Wash were walked. Paleostream directions and alterations of the sandstones were observed and recorded on a base map. No important new mineralization was discovered-and the area is considered to be of no commercial significance if judged by the outcrops alone. However, a vast amount of Salt Wash lies at slight depth directly to the east of the investigated area.
Date: July 13, 1954
Creator: Hanshaw, Bruce B.
Object Type: Report
System: The UNT Digital Library
Hydrologic and Tracer Studies in Mohawk River at Knolls Atomic Power Laboratory (open access)

Hydrologic and Tracer Studies in Mohawk River at Knolls Atomic Power Laboratory

Preface: In 1948, the U.S. Geological Survey, in cooperation with the Atomic Energy Commission, initiated a study of the hydraulics and hydrology of Mohawk River in the vicinity of the Knolls Atomic Power Laboratory (KAPL) near Schenectady, N.Y. The purpose of this study was to determine the probable effects of release of low concentrations of radioactive wastes from the Laboratory to Mohawk River.
Date: July 1959
Creator: Simpson, Eugene Sidney; Beetem, W. A. & Ruggles, F. H., Jr.
Object Type: Report
System: The UNT Digital Library
Design and Test Analysis of the Magnetic Jacking Positive Latch Control Rod Drive Mechanism (open access)

Design and Test Analysis of the Magnetic Jacking Positive Latch Control Rod Drive Mechanism

Abstract: Testing of the Latch Type Magnetic Jack Control Rod Drive Mechanism was undertaken to determine its feasibility for application in the Yankee Atomic Electric pressured water reactor.
Date: July 1959
Creator: Balog, L. J.; Bishop, A. A. & Widmer, Thomas F.
Object Type: Report
System: The UNT Digital Library
Organic Cooled Reactor Study [Part 4]: 75 Mw Power Plant Conceptual Design (open access)

Organic Cooled Reactor Study [Part 4]: 75 Mw Power Plant Conceptual Design

From introduction: This volume presents the results of a conceptual design study for an intermediate size, 75 megawatt power plant utilizing an organic moderated and cooled reactor.
Date: July 1959
Creator: Bechtel Corporation
Object Type: Report
System: The UNT Digital Library
Preliminary Report on a Uranium Occurrence and Regional Geology in the Cherry Creek Area, Gila County, Arizona (open access)

Preliminary Report on a Uranium Occurrence and Regional Geology in the Cherry Creek Area, Gila County, Arizona

Introduction: A reconnaissance of the Black Brush property was made by geologists of the Atomic Energy Commission in March, 1955. This anomalous area was located by an earlier airborne radiometric survey. the examination consisted of preliminary sampling and surface and underground radiometric traversing.
Date: July 1956
Creator: Sharp, Byron J.
Object Type: Report
System: The UNT Digital Library
Two Stage Leaching Tests on Utex Ore (open access)

Two Stage Leaching Tests on Utex Ore

Introduction: The object of this test work was to determine the practicability of a two-stage leach using ion-exchange as the method of uranium concentration.
Date: July 22, 1954
Creator: Stanley, Alan; Eisenhauer, Robert & Richardson, Stanley
Object Type: Report
System: The UNT Digital Library
Development of an Ion Exchange Process for the Recovery of Vanadium (open access)

Development of an Ion Exchange Process for the Recovery of Vanadium

A process for recovering vanadium from acid leach liquors by ion exchange using either columns or resin-in-pulp has been developed. The process is economically feasible, and operating techniques were developed which made the process practical from an operating standpoint. The theory, chemistry, and characteristics of the vanadium ion exchange process are fully discussed.
Date: July 30, 1954
Creator: McLean, D. C.; Hollis, E. T. & Eisenhauer, R. A.
Object Type: Report
System: The UNT Digital Library
Polonium (open access)

Polonium

From foreword: This is a report on the efforts of Monsanto Chemical Co. to solve some of the chemical problems involved in the atomic energy program.
Date: July 1956
Creator: Moyer, Harvey Vernon; Gnagey, Lloyd B. & Rogers, Adrian J.
Object Type: Report
System: The UNT Digital Library
Advanced Pressurized Water Reactor Study [Part 1]: Phase 1 Report (open access)

Advanced Pressurized Water Reactor Study [Part 1]: Phase 1 Report

From preface: This report covers Phase I of the authorized work, consisting of determination of the specific reactor concept and size for the most economic reactor, preparation of a reference design of the most promising concept and estimated capital and generating costs, evaluation of the variations in cost as a function of unit size, and evaluation of the reductions in ultimate costs for a power station having multiple units of the same type.
Date: July 1959
Creator: U.S. Atomic Energy Commission. Division of Reactor Development.
Object Type: Report
System: The UNT Digital Library
Advanced Pressurized Water Reactor Study [Part 3]: 235 Mw Coal-fired Generating Plant (open access)

Advanced Pressurized Water Reactor Study [Part 3]: 235 Mw Coal-fired Generating Plant

"This study is one of four initiated in 1958 by the Division of Reactor Development, U.S. Atomic Energy Commission, to assess the feasibility of power generation through the use of certain types of nuclear reactors. These studies are available from the Office of Technical Services, U.S. Department of Commerce, Washington 25, D.C."
Date: July 1959
Creator: U.S. Atomic Energy Commission. Division of Reactor Development.
Object Type: Report
System: The UNT Digital Library