Report issued by the University of California Radiation Laboratory discussing an experiment in which a system was designed and built to load titanium with deuterium gas of a high purity. It discusses the results and the parameters affecting the amounts and purity of the absorbed gas.

One of a series of experiments to test the radiation corrosion of Zircaloy-2 and other possible reactor construction materials in UO2SO4 solutions under various radiation intensities, temperatures, solution compositions, and velocities of flow past specimens.

Unit developed at Knolls Atomic Power Laboratory for extraction and overcomes the disadvantages of the batch countercurrent units currently in use.

Report describing the Hanford Atomic Works' Plutonium Recycle Test Reactor, its siting concerns, operation, and safety concerns.

Report discussing the results of fill and drain holes for hydrostatic pressure tests on head knuckle radius of forged-steel gas storage cylinders.

Cycle study performed on a closed loop Brayton cycle incorporating a gas-cooled nuclear reactor, regeneration, and compressor intercooling. The purpose of the study was to determine the effect of various cycle parameters on efficiency and cost.

From introduction: "Preliminary design and analysis of the 300 MWe core."

Information on experimental facilities and reactors.

Quarterly progress report discussing activities related to the Vallecitos Boiling Water Reactor (VBWR) and related facilities.

From introduction: A trip into the Henry Mountains area occupied the days from March 6 to 9, 1951, inclusive, excepting March 7, which was used to examine Reo Hunt's deposit in Poison Spring Wash. Observations were made on stratigraphy, regional geology, and the locations of the known deposits of uranium and vanadium.

From introduction: Oil and gas wells and related facilities of the Baxterville field were surveyed to document any physical changes resulting from the Salmon Event. All such structures within a 5-mile radius of Ground Zero were examined and photographed in detail.

From introduction: The Bluff-Salt Wash contact was mapped on aerial photographs. Mines and prospects were also plotted on the photos. The mines and prospects were studied and a brief description of the mineralization and its occurrence was written. These field notes, which will be given to Hatfield and party, contain data on the presence of carbon and fossil logs, lithology of the gangue rock, sedimentary structures, etc. Regional structure and evidence for igneous activity were also noted.

From introduction: "A detector system with the advantages of a liquid counter, but without the severe requirements on sample preparations, has been devised and is the basis of the present experimental investigation."

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."

The following report provides information conducted during histological observations made on the anatomy of female mice who have been exposed to 400 arbitrary units of slow neutrons.

This report helps determine tritium in the range of 0.1 to 100% in other gases using an ion chamber that is analyzed within this report.

The following report describes and foretells the situation in medium in which neutrons are being (a)produced as fast neutrons, (b) slowed down to thermal speeds by impacts with nuclei, and (c) absorbed by nuclei in such a manner that sometimes fresh fast neutrons appear at the place where a thermal neutron has just appeared.

Abstract: "A small low impedance flux monitoring device has been built which utilizes the heating (and consequent chance in resistance) of a boron coated platinum wire. Feasibility tests in the Argonne-GP-3 reactor indicate that it may develop into a wide range instrument, particularly useful at high flux levels. Design and constructional details of the bolometer and its associated circuits are given. The circuitry is somewhat unique since it is in effect an all electronic self-balancing bridge. Future lines of research are suggested to solve some of the remaining problems."

Abstract: "A uranium-titanium constitution diagram is presented. There is complete solid solubility between titanium and gamma uranium above about 2100 F. Only one compound exists in the system. It has a hexagonal structure based on U2Ti. It has a fairly wide range of stability, particularly on the titanium side. Beta-titanium solid solution decomposes eutectoidally into alpha titanium and compound at 1150 F. Eutectoid composition is about 72 atomic per cent titanium. Gamma-uranium solid solution decomposes eutectoidally at 1325 F into beta uranium and compound. Eutectoid composition is about 6 atomic per cent titanium. Beta uranium and compound react peritectoidally at 1233 F to give alpha uranium. Solubility of titanium in alpha and beta uranium is low as is the solubility or uranium in alpha titanium."

"Neutron total cross sections for bismuth and uranium have been measured in a good geometry transmission experiment, using a time-of-flight instrumentation. The source of neutrons was the stripped deuteron beam of the 184-inch synchrocyclotron. The results are shown in Fig. 1. Uncertainties are shown in terms of standard deviations, due to counting statistics only, and to energy channel width."

Abstract: An analysis of the lid tank neutron data for Pb-H2O and Fe-H2O is made. "Effective" fast neutron cross sections for the metals are obtained. This is based on the "one collision theory" of shielding. Values are 3.4 barns for Pb and 2.0 barns for Fe. These compare very well with those obtained by Albert and Welton based on other lid tank data and another method of calculation.

The following report analyzes various experiments made to discover factors that may affect properties of extruded compacts of crystal bar zirconium.

The following report discusses special shielded containers, called coffins, that are used for removing beam hole plugs from the reactor, transporting them to plug storage and inserting them therein. This report focuses on the handling of dummy and experimental beam hole plugs.

The following report discusses an equation derived by which the maximum allowable concentration in the atmosphere of a beta-omitting isotope for which lung damage is the limiting consideration can be calculated.