Abstract: The boron-carbon equilibrium diagram has been determined by X-ray, metallographic, and thermal analysis of sintered and arc-cast alloys. A single carbide having a range of solubility from approximately 9 to 20 a/o carbon and melting congruently exists in the system. The terminal solubility of carbon in boron is 0.1-0.2a/o. The freezing reaction at the composition and melting temperature of elemental boron; there is a eutectic reaction at 29a/o carbon and 2375 degrees Celcius. No allotropy of boron was observed.

The following report follows the studies of electroplating on uranium and concurrent metallurgical clodding.

The following document is a note describing the building process of an improved nuclear density gauge in comparison to previous gauges, within the interval of July 1 to August 1, 1959.

"In the past ten years quantities of alpha-, beta-, gamma- and neutron-emitting isotopes handled in enclosures have increased from microcuries to kilocuries. Contaminated-atmosphere problems have increased accordingly. Developments at Berkeley are reviewed with particular emphasis on recent equipment, viz: a multiple-purpose gas scrubber and a total-capture system for slug-dissolver off gas."

Introduction: "The carrier (pyroelectric) concentration method is commonly used in the spectrographic analysis of plutonium metal. This report describes work which lead to substantial improvements in accuracy, precision and ease with which the analysis is made. Included are data from analyses of plutonium metal by the original and the improved carrier methods, and the cupferron extraction method."

The following document describes suggestions on the application of the A-48 ion accelerator beam currents to the Sherwood Program.

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.:

The use of uranium mononitride as a nuclear fuel is being considered for a number of high temperature applications. In comparison with the most often applied high temperature fuels, UO2 and UC, one finds that UN has a combination of the high melting point of UO2 and the thermal conductivity and high uranium density of UC. However, interest in UN is often dampened by qualitative indications of its low thermal stability and by lack of experimental thermodynamic data. Is is the purpose of this study, therefore, to provide a quantitative measure of the thermal stability of UN and to establish some of its thermodynamic properties.

Abstract. An apparatus for measuring the thermal conductivities materials which are moderately good conductors of heat is described. Results obtained with a sample of pure Th are given on p. 10, 12, and 13.

The following report follows a test with the purpose of determining the effect upon image fidelity by exposing a television camera to high intensity radiation over an extended period. Provided later in the report are notes on the design of the utiliscope camera used for these tests due to notable design features.

The following report briefly covers broad general features of the chemical studies to be used by the Atomic Energy Commission in considering future work on the chemical studies of phosphate rock and shale.

The purpose of this report is to present information on materials which can possibly be employed in the HF-H₂O-H₂SO₄-system in the extractive distillation process to be investigated at NBL.

Abstract: A description is given of the design and operation of a windowed autoclave system employed in the study of corrosion by pressurized hot water. The device has been used to obtain time-lapse motion pictures of the swelling and rupture of deliberately defected zirconium-clad uranium specimens. A method is described by which corrosion rates were calculated from pressure and temperature measurements. A typical set of pictures taken during a test is presented, and corrosion rates are reported for uranium-0, 5, 10, 15, and 20 w/o zirconium alloys subjected subjected to 600 F water.

Purpose: "This test was conducted to gain information and experience in the handling of heavy aggregate concrete. The results from this test were to establish procedures for a subsequent program -- "Construction Test of High Density Concrete Shielding.""

There have been numerous independent suggestions to use high speed shocks to heat deuterium gas to thermonuclear temperature (E. Teller, R.R. Wilson, H. Grad, W. Marshall)², and extensive experimental work in this field is being carried on by, e.g., Kolb³, and S. Janes⁴. Our own work in this field has been directed towards a fundamental understanding of the strong shock process in the limit of no particle collision, to find out if within this limit the ion heating following the passage of the shock is large enough to give rise to a thermonuclear reaction.

A simple method of solving for the phase shifts of the pion-proton scattering is presented. The rapid solution afforded can be utilized, as the Ashkin diagrams have been employed, to give starting values to an electronic computer or alternatively to analyze with more ease the variation of the phase shifts as a function of the input data in terms of the coefficients of the angular distributions. A new plot of a function of the total cross section versus the pion energy is introduced. The nearly straight line resulting should help to evaluate the experimental data.

In certain phases uranium processing it is poss!ble for operating personnel to acquire internal deposits of uranium. This body burden can be acquired by injection, as in contamination of a wound, by ingestion, of by inhalation. In order to estimate internal exposures, some means of determining the location and extent of these internal deposits is essential.

This review covers: (a) The continuous countercurrent ion exchangers which have been described in the patent and/or technical literature. (b) Some of the other moving bed processes which are similar in mechanical arrangement to a continuous countercurrent ion exchange and which might have certain features adaptable to an ion exchange unit. (c) The auxiliary mechanical devices which are or may be used in an ion exchange apparatus.

An improved heat sink for space vehicles was proposed in ORNL-CF-59-1-21. Subsequent work on the problem has indicated that there is a substantial probability of a puncture of such a radiator by meteors. To meet this problem a modified geometry has been evolved for which the probability of a meteor puncture should be reduced by a factor of at least 100 relative to the radiator of the original proposal at the expense of an increase in radiator weight of possibly 30%. This memorandum outlines the approach to the problem and a series of similar promising solutions.

The following report analyzes and calculates the accuracy of a procedure that processes independent source neutron cards in the Monte Carlo method.

The following document describes x-ray diffraction measurements for an approximate crystal structure for the beta phase of metallic uranium.

The following report analyzes the characteristics of eight chelated uranium complexes and seven uranium ammines, prepared from the reaction of organic solutions of uranium salts with complexing agents and organic bases.

Abstract: "The heat of solution of thorium sesquisulfide was determined in 6.000 molar HCl at 25 C to ascertain the stability of the thorium (III) halides. The molal heat of formation of Th2S3 from rhombic sulfur and crystalline thorium is calculated as 258.6 kcal."

This report follows a study that was undertaken to evaluate the practicality if removing the heat from the reactor cooling water by means of a "flash cooler" and to compare its economics with that of the conventional heat exchange system.