"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.

Annual report submitted by the Girl Scouts of the United States of America to Congress describing highlights from 1957, activities, finance, organizational leadership, and other information about scouting programs.

Report detailing the history and biological aspects of the pygmy seahorse, including its sex ratio, breeding season, growth patterns, and more.

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 …

In this document it is proposed to describe the plant site and to outline the nature of the pile in order to show the specific design and layout requirements for the production of plutonium by nuclear synthesis. The selection of the plant site involved a number of special considerations. An essential requirement was a large dependable supply of relatively pure water that remains at a fairly low temperature throughout the year. A large source of power was required to circulate the tremendous quantities of water. The potential dangers connected with the high energies of the nuclear reaction and the formation of a large quantity of radioactive by- products required large distances between each operating section of the plant, and between the plant and main rail and highway routes. The plant site layout and reactor areas are discussed in the first part of the chapter, followed by a functional description of the more essential pile components. The chapter concludes with a discussion of reactor instrumentation. 24 figs., 2 tabs.

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The purpose of this report is to examine the theory of radiation damage to obtain an idea of the extent of this damage.

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The ultimate achievement of a research and development program at Sandia. Corporation, as at any other AFX or DOD project, is the physical design of a component or weapon system of high reliability. The design accomplishment is initially established when the basic drawings and specifications are released for production. These drawings and specifications are often based on engineering evaluations of bread- .board and early so-called & quot;gold plated prototypes. However, the design accomplishment is not completed until the item is manufactured by production tools and performs satisfactorily, meeting all the requirements specified in the engineering and manufacturing information. It is only at this stage that we have initial assurance that we may proceed with quantity production. This transition from essentially handmade prototypes to a production-tooled reliable product is a crucial one in any design development program, but it is especially as when the end product is complex and extremely high reliability is required.

In order to investigate the rupture stability of uranium elements irradiated at power generations per unit length larger than those encountered in natural uranium fuel elements, three partial columns of 1.44% U{sup 235} enriched, internally-externally cooled, uranium elements were irradiated in PT-IP-1-A. After discharge and examination of the fuel elements 25 pieces (182.5 pounds) of this metal were available for special analysis of U{sup 235} burnout and plutonium content. The average exposure of these pieces was 2,187 {+-} 6% MWD/Ton. The purpose of this document is to summarize some calculations of buildup of plutonium isotopes and burnout of U{sup 235} in an attempt to correlate calculations with the results from experimental analysis.

Beginning in February, 1958, a sufficient quantity of seven-inch dip canned I & E depleted uranium fuel elements was prepared for irradiation to produce eleven kilograms of plutonium, containing at least twenty per cent of the Pu-240 isotope, as authorized by the Atomic Energy Commission. Subsequently, eighty-four columns in C reactor were partially charged with the finished depleted fuel under PT-IP-132-AC. To date, ten depleted ruptures have been sustained, after being irradiated six to eight months toward a planned accoumulated goal exposure of 210 MWD per column or a total irradiation time approximating 12--14 months. The mechanism and cause of these failures is being thoroughly investigated. This document summarizes the fabrication history, irradiation experience to date, rupture examinations, and an investigation of process conditions which may have contributed to the high incidence of ruptures.

Attempts are reported to obtain records of transient air temperatures at selected locations in a blast biology underground shelter during nuclear explosions. No records were obtained due to failure of equipment. An evaluation of thermal burns was made on Chester White pigs used as test animals. One pig in the entrance and one about three feet inside the door received severe burns, while animals away from the entrance and those in the slow fill side received no burns. Possible explanations are discussed.

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.

The status of development studies being conducted on a pebble bed power reactor is outlined. The items discussed are fuel element manufacture, stability, and reprocessing, and component development. (D.L.C.)

This report addresses the advanced energy sources and conversion techniques.