"Several multiplier phototubes produced by England, Russia, or Switzerland were evaluated for amplification, photocathode sensitivity, photo-electron collection efficiency, cathode uniformity, and dark current. A description of the various tubes by designation numbers is given, along nth a description of techniques and equipment used in testing."

Results of an initial examination of non-fuel-bearing materials for the Marine Gas Cooled Reactor are presented. Areas given specific attention include structural and cladding materials and graphite moderator. Other areas not included because of classification include zirconium hydride moderator and control materials. In each report section, available pertinent information is summarized and a plan for future work is given.

Technical report was prepared by the Health and Safety Laboratory (HASL) with the objective of presenting a current picture of the Strontium Program. Abstract: Strontium 90 levels in fallout, milk, canned fish and tap water are summarized for data available up to July 28, 1958. Original data submitted during the month of June and the first two weeks in July are included as an appendix. Data are presented to show the amount of Strontium 90 in fallout at sampling stations within and outside the United States.

Phase I - Plant Transient Analysis. Behavior of the basic and refined kinetic models differs only slightly. It is therefore suggested that the basic model be used in any studies where the improvement in fidelity attainable fro the refined model is not warranted by the complexities introduced by the addition of function generator to the analog circuitry and derivation of the function to be programmed. The parameter responses of both kinetic models appear to be essentially similar to those of the plant with the exception of the primary pressure. In the pressurizer analysis it was noted that the primary system pressure surges of the model should be higher than those of the plant because of the adiabatic steam compression assumed in the model derivation. the fact that the mode surge is very much greater indicates that the compression process is far from adiabatic. A more detailed and complex model of the pressurizer, one that evaluates heat transfer in the steam pocket boundaries, would therefore reduce the costly conservatism otherwise necessary in the specification of pressurizer vessel size. Phase II - Xenon Reactivity Transients. On the basis of this study an analog computer circuit has been presented which accurately represents bank …

A report discussing a more general analysis of "the relation between plasma pressure in the Astron [Thermonuclear Reactor] and the magnetic field of the E-layer" which is described in UCRL-5032. The analysis given in this report has "no restriction to the exponential form and [satisfies] the condition that the pressure at the axis shall be zero."

"This bibliography is a compilation of titles to unclassified reports, journal articles and conference papers written by members of the University of California Radiation Laboratory, Livermore and Berkeley, relating to Project Sherwood (Controlled Thermonuclear Reactions) from 1953 through 1957."

A report about thermal-conductivity and electrical-resistivity measurements made on a uranium-1.5 w/o zirconium alloy surrounded by NaK enclosed in a Zircaloy-2 capsule which were in poor agreement with measurements made directly on a uranium-1.5 w/o zirconium specimen.

A report pertaining to the thermal-conductivity and electrical-resistivity measurements of uranium encapsulated in zircaloy-2 and surrounded with NaK as a heat-transfer material which is not in agreement with results obtained from unclad uranium.

A report about the fabrication of dummy fuel-pls assemblies which are to be used in the engineering test loop at the MTR.

A report about equipment constructed and methods being explored to determine the effect of irradiation on the thermal and electrical conductivities of encapsulated uranium and on the thermal conductivity of UO2.

A report about the start of preliminary measurements of the thermal conductivity of clad uranium and Zircaloy 2 prior to irradiation.

A report dealing with thermal-conductivity measurements of uranium and UO2 to determine the effect of irradiation on both of these two materials.

From abstract: A team consisting of R. A. Lindblom, S. A. Mayer, R. G. Young, W. L. Chenoweth, R. F. Droullard, and I. T. Fisk made a reexamination of the Anderson mine (Uranium Aire) of Interstate Oil and Development located near Wickenberg in Yavapai County, Arizona. The field examination was made from August 22, 1958 to September 2, 1958. This team was formed to resolve differences between company and AEC ore reserve estimates. A cooperative effort in which the company supplied labor, limited additional drilling and both parties were in attendance during the sampling resulted in the collection of additional data. Special attention was given to assessing the in-hole assaying with radiometric equipment by IOD and AEC, evaluation of tonnage factors, moisture content, continuity of ore, and current mapping of stripped and mined areas.

Originally issued as S and P 1963A, Parts I and II. This report covers a design and feasibility study of a pebble bed reactor-steam power plant of 125 megawatt electrical output. The reactor design which evolved from this study is a two-region thermal breeder, operating on the uranium-thorium cycle, in which all core structural materials are graphite. Fuel is in the form of unclad spherical elements of graphite, containing fissile and fertile material. The primary loop consists of the reactor plus three steam generators and blowers in parallel. Plant design and system analysis including cost analysis and capital cost summary are given.

Abstract: This report outlines the general techniques developed for replacement of PRE in-cell equipment or equipment components.

Abstract: This report presents a description of the Organic Moderated Reactor Experiment (OMRE), of the hazards associated with this experiment, and all of the safeguards taken to ensure the safety of the operating personnel and the population of the surrounding area.

From abstract: "A preliminary design is presented for a boiling water reactor power plant for a propulsion of a 22,000 SHP commercial tanker."

Progress report discussing projects and work completed by the University of Michigan Department of Chemistry 1957-1958.

Report of the annual conference on weights and measures, hosted by the U.S. National Bureau of Standards in Washington D.C. It includes conference proceedings, a list of attendees, information about committees and officers, and other reports or commentaries discussed at the meetings.

Report examining the problems of handling liquefied gases and discusses the feasibility of transporting them through piping systems.

From introduction: "This report provides background information regarding the study results presented in the first volume of this report and provides information resulting from the studies made on the gas cooled reactor concept."

Study of factors, such as the average particle size and particle-size distribution, which affect the fluidization properties of uranium trioxide powders.

Report documenting the systems, operating procedures, and design of the Oak Ridge National Laboratory's gas-cooled reactor.

Report documenting the systems, operating procedures, and design of the Oak Ridge National Laboratory's gas-cooled reactor.