This is a summary report of various technical projects relating to uranium.

From Abstract: "The heat treatment and mechanical properties of four zirconium alloys...were investigated. Tensile, hardness, Jominy end-quench, and metallographic data constitute the basis for much of the report. Other data reported include the results of high-temperature creep, tensile, hardness, cold rolling, thermal-cycling, and dynamic-modulus tests." A connection is made between the behavior of these four alloys and more alloys in the zirconium-uranium system.

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."

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]

Abstract: "A scheme is discussed in which D+ ions would be accelerated to about 100 kev in a conventional accelerator, then be sent through a gas target frmo which about half the ions would emerge neutral with very little scattering or energy loss; the neutral beam would then cross into a magnetic field and part of the atoms would be ionized and trapped by colliding with the already trapped ions. The smallest mirror machine with a central field of 30-40 kilogauss, 2;1 mirror ratio and β = 01 to 0.5 that would trap most of the neutral beam in the steady state, would be about a meter in diameter and require the order of hundreds of amperes of D+ ions into the neutralizer. The smallest stellerator with a field of 30 kilogauss and β = 0.1 that would trap most of the neutral beam would be about a meter long and require about 10 amperes of D+ ions. A preliminary mirror machine experiment that might be done using the 1/2-ampere, 100-kev D+ beam from the UCRL spare MTA injector is discussed. A method of starting these machine is discussed."

Abstract: Horse Mesa is in the Navajo Indian Reservation directly on the Arizona-New Mexico state line. Uranium-vanadium deposits in the Salt Wash sandstone which caps the Mesa are fairly widespread and small tonngges have been shipped from two mines. The deposits lie 60 to 75 feet above the base of the Salt Wash formation and possibly trend northwest parallel to ore trends on King Tutt Mesa, a mile northeast. Carnotite and vanoxite are the principal ore minerals. About 6,000 feet of wagon drilling is recommended to test two favorable areas. Continued exploration should be governed by results of this first stage drilling.

Introduction: Vanadium ore is being mined at many places in western Colorado, southeastern Utah, northeastern Arizona, and northwestern New Mexico (fig. 1). Eight mills in this region produced about 4,300,000 pounds of V2 05 in 1942, representing about 90 percent of the vanadium obtained from domestic sources. Although ore production has mostly exceeded mill capacity since 1937, production during the last half of 1942 averaged only about 19,000 tons or ore a month, whereas the capacity of these mills total about 22,000 tons a month. At the expected rate of ore production, ore stockpiles will be exhausted sometime in 1944, and these mills will then have excess capacity. With more intensive prospecting than now practiced, however, it is believed that sufficient reserves can be indicated to sustain capacity operation of these mills for several years. This memorandum is prepared to specify those areas that are considered most favorable from a geologic standpoint for developing large reserves of vanadium ore by prospecting. It is based on intensive studies by the Geological Survey since 1939 in most of the areas that produce vanadium ore.

From introduction: The general distribution of known deposits of vanadium-bearing sandstone, which also contain some uranium and radium, is shown in figure 1 1/ and Exhibit A, plate 53. 2/ During 1939-41 the Geological Survey made detailed geological studies of these deposits in the Uravan district, Montrose County, Colorado, as well as preliminary examinations in other parts of the Colorado Plateau vanadium region. In 1942 detailed geological studies were made o the deposits in the Egnar-Slick Rock district, San Miguel Co., Colo.; 3/ the Carrizo Moungains district, Navajo Indian Reservation, Arizona and New Mexico; 4/ the Placerville district, San Miguel County, Colo. 5/ and the Monticello district, San Juan Co., Utah. 6/ Since May 3, 1943, the Gelogical Survey has guided the Bureau of Mines program of prospecting these deposits in parts of Colorado and Utah.

From foreword: The objective of this study is to determine the practical and economic use of nuclear for the production of electric power in the Pittsburgh district.

Abstract: Ground effects resulting from Blanca, Logan, Evans, Tamalpais and Mars events of HARDTACK Phase II underground explosions were measured by strong-motion and teleseismic seismographs out to distances of nearly 100 miles.

From summary: This report summarizes the work performed in a brief study made for the AEC of boiling water reactor power plants in the 5 to 40 eMW output range.

Foreword: In early 1959 the U.S. Atomic Energy Commission initiated a study to assess the feasibility of low-level power generation through the use of certain types of small-sized nuclear reactors.

From introduction: This report discusses AEC-sponsored nuclear superheat meetings whose primary purpose is to keep the AEC contractors engaged in nuclear superheat projects abreast of the overall AEC superheat program and to provide a means for the exchange of current technical information.

Abstract. A review of all work on uranium hydride published in the CC, CT, CN and CE reports to January 1, 1944, is presented. Some additional information not yet published has been included, so this report includes all data known from the above sources and at Ames to the above date. This report supersedes all previous report on uranium hydride coming out of the Ames laboratory.

Introduction. the colorimetric determination of iron based on the formation of the colored ferrous-1,10-phenanthroline complex has been used successfully by a number of investigators. In this technical report, its adaptation to the routine determination of iron in cerium, thorium, and beryllium metals and their compounds is described.

Technical report describing the purification and separation by distillation of UO2F2 from D2O. In the experiment which is discussed 2,129.6 lbs of UO2F2 were dissolved in 6,605 lbs of D2O. The average isotopic purity of the D2O decreased during the distillation from 99.77% to 99.73%. The dissolved impurities were less than those present originally in the heavy water.

Summary: The following narrative interspersed with figures and attached reference exhibits is designed to acquaint the reader with the scheduling procedure developed at ORGDP, trial results and evaluation, subsequent improvement, further application, and use in conjunction with our IBM 7090 Computer.

From conclusions: There is a close enough correlation for most metals to give the chart some utility in estimating vapor pressure of metals.

From abstract: "Experiments covering the coprecipitation of Thorium and Uranium peroxides are described on synthetic and actual 1300 cycle machine wash effluents."

Abstract: Test distillations were made with Kinney and diffusion pump oils under vacuum in order to determine accurately the temperature range over which satisfactory distillate may be collected. Also recommendations are made as to the most advisable type of heating equipment necessary to produce the required heat and maintain the desired temperature. In addition, several important refinements in the distillation equipment were checked for operational characteristics and for their efficiency in aiding the production of uranium-free distillates.

The following report discusses the results of a survey that was initiated to ascertain the availability of uranium hydride in tonnage quantities.

Report that outlines the major issue of reactor theory and asymptotic reactor theory. Uncommon reactor theory results are also discussed and unanswered questions regarding reactor theory are presented by the author.

The purpose of this report is to summarize the work done at KAPL on physical properties of high density concretes.

From introduction in Volume I: Volume II describes those programs established by the operator to assure the safe operation of the reactor.