Introduction. With the imminence of non-destructive landings of small instrumented payloads on the moon, many suggestions are being put forth as to methods of analyzing its surface. It is the purpose of this report to present a body of information which, it is hoped, will be useful in examining the feasibility of an early nuclear experiment to determine the elemental constituents of the lunar surface. The reasons for considering a nuclear approach is that it may be possible to perform an analysis without complex and elaborate manipulations, sample preparation or rigid geometrical constraints. Only those experimental designs which come within the presently-available or very-near-future general boundary conditions on weights, power, vehicles, etc., are discussed. The general approach is to consider the bombardment of the lunar surface with various nuclear beams and to examine the possible nuclear reactions which are know to be dependent on the mass and charge of the irradiated material. Then, those resultant radiations are sought which can be detected with little-or-no loss or distortion of the information which they contain.

There has been a revival of interest over the last few years in the theory of the high energy photoelectric effect. this problem has been especially clarified by the work of Pratt. Others have also contributed as will be noted below. In particular these workers have shown that the formula for photoelectric absorption of hard gamma rays by the two K electrons of an atom, which is often quoted in the literature, is too large for heavy elements by a factor amounting to approximately 2 for Pb. It turns out that the error is due to a faulty procedure described in the reference (3), p. 396 for obtaining an estimate of the exact formula.

Technical report. From Abstract: "A combination densitometer and analog computer is described which determines radiation exposure of photographic film used in personnel badges. The range of the instrument is 0 to 300 mr gamma and 0 to 300 mrad beta plus gamma. A novel phototube circuit is used to obtain logarithms directly."

Technical report. From Abstract: "A process was developed for manufacturing aluminum-clad slugs containing UO2 or ThO2 dispersed in an aluminum matrix. In this process a mixture of the oxide and aluminum powder is cold compacted to form the billet core, which is then coextruded with an aluminum sheath to produce the clad slug."

Introduction: Confidence limits as a mathematical tool are applicable to many development engineering and production engineering situations. In order to make confidence limits readily available to engineers, a computer was designed which will approximate certain confidence limits.

The present report describes the evaluations conducted with plated-through connections produced by techniques used by some of the prominent fabricators of printed circuits.

This bibliography contains 147 references on the fabrication of beryllium. References are also given on the brazing, casting, cladding, extrusion and welding of beryllium and some beryllium-rich alloys. The bibliography is limited to the period 1950 - 1959. references are arranged alphabetically by title, with author and subject indexes provided. Sources used in compiling this bibliography are: Abstracts of Classified Reports, ASM Review of Metal Literature, Bibliographies of Interest to the Atomic Energy Program - Classified and Unclassified Versions, Engineering Index, Nuclear Science Abstracts, TISE, List of Bibliographies in the Atomic Energy Program.

Preliminary study to determine the technical and economic feasibility of a 315 eMW High-Temperature, Integral, Liquid Metal Fuel Reactor (HTIR).

Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.

Report issued by the APDA over studies conducted on the irradiation of fuel pins in nuclear reactors. As stated in the introduction, "results of these tests have verified predicted high-temperature allowable burn-ups and showed that under certain conditions, excessive swelling could occur at low temperatures" (p. 5). This report includes tables, illustrations, and photographs.

The Babcock and Wilcox Company (B&W) proposes to construct and operate a Nuclear Test Reactor on the grounds of the Company's integrated nuclear facilities site, Mt. Athos, near Lynchburg, Virginia. This preliminary Summary Hazards Report present to the U.S. Atomic Energy Commission (AEC), Division of Licensing and Regulations, a description of the facility, the characteristics of the proposed site, and an evaluation of potential hazards to the area surrounding the site of operation.

Abstract: A portable assembly for handling and shipping OMRE fuel elements is described and details of its operation are given. Problems of heat transfer and radiation shielding are discussed, and detailed analysis are presented.

Partial abstract: "The direct utilization of fission fragment recoil energy in chemical production shows outstanding promise as a significant application of atomic energy. Highly efficient use of the liberatied energy under high temperature conditions and with unusually rapid quenching is within engineering grasp. This contract has covered a measurement of the efficiency with which nitric acid can be produced by such a process under industrial plant conditions. Equipment, techniques, and instrumentation were developed and perfected which permitted an in-reactor yield measurement using fissile smoke dispersed in a 4:1 nitrogen-oxygen gas mixture at 1000 psi and 200 C" (p. iii).

Technical report describing the methods used for forming wave guides for installations of microwave diagnostic systems for use in Project Sherwood. A machine designed by the author is described along with details of its use.

From introduction: This report details the seismic measurements by the USGS during the pre-Gnome high-explosives tests near Carlsbad, New Mexico.

Report the describes a simple accurate simulator that can predict the ion trajectories in and ion gun for certain electrode geometries.

This is a selected bibliography of books, journal articles, and unclassified reports published on the state of matter at high pressure from 1950 to October 1959. Sources consulted were: Physics Abstracts, Nuclear Science Abstracts, Geophysical Abstracts, Library of Congress Monthly Index of Russian Accessions, and Chemical Abstracts.

Abstract: This technical report summarizes the data obtained in a recent literature survey conducted to determine the effects of neutron irradiation on the impact and other mechanical properties of both ferritic steels and austenitic stainless steels. The survey was primarily aimed at obtaining sufficient data on the behavior of pressure vessel steels at high integrated neutron flux levels in order that a reference material of construction could be selected for the SM-2 (APPR-1B) reactor vessel. Materials studied in this literature survey included carbon and low alloy steels such as: ASTM A-212B, ASTM A-201, ASTM A-301B (CR-Mo), ASTM A-106 (coarse and fine grained), ASTM A-285, ASTM A-302B (Mn-Mo), ASTM A-353, ASTM A-203 Grade D, E-7016 carbon steel weld metal, USS Carilloy T-1, HY-65 and HY-80. In addition, Types 304 and 347 stainless steels were also investigated as representative austenitic materials which might be used in pressure vessel construction. A careful evaluation was made of the irradiation induced changes in the mechanical properties of the above materials. The ferritic steels were evaluated primarily on the basis of increases in transition temperature due to irradiation and decreases in the amount of maximum energy absorbed prior to ductile failure. Factors such as industrial experience, …

A geometrical treatment has been used to outline the theoretical properties of optical fibers which are imperfect as well as geometrically and optically perfect. Experiments have been performed to measure some to the optical properties of individual fibers and fiber bundles.

Technical report. From Abstract: "The thermal conductivities of aluminum-lithium alloys containing up to * wt % lithium were determined at temperatures between 125 and 260ºC. The addition of lithium to aluminum sharply reduces the conductivity from 0.60 cal/(sec)(ºC)(cm) for pure aluminum to 0.22 cal/(sec)(ºC)(cm) for 2 wt % alloys; further addition linearly and more gradually decreases the conductivity to 0.16 cal/(sec)(ºC)(cm) for a 7.9 wt % alloy."

This document presents the bases for those PRTR Process Specifications involving considerations of heat transfer and fluid flow. It will be noted that some of the bases incorporate information gained from laboratory experiments with electrically heated test sections simulating PRTR fuel elements. These experiments are described in some detail elsewhere.

Report that discusses programs to determine the transportability of the ML-1 nuclear power plant via railroad, tractor-trailer, and aircraft.

Abstract. A conventional time-to-height converter operates by charging a capacitor to a voltage proportional to a time interval. To convert short time periods, the circuitry is limited by the stray capacities. A system was designed in which the Vernier chronotron principle is utilized to time scale the input time before time-to-height conversion. Accuracy is also improved over that attainable with conventional systems. The use of transistors is facilitated by the system design.

This bibliography contains 145 references on radiation effects on aluminum, elastomers, and lubricants. Also included are references on radiation units and conversion factors. The bibliography is limited to the period 1950 through 1959, with the references arranged alphabetically by title in five categories. An author index is provided. Sources used in compiling this bibliography are: Abstracts of Classified Reports, Bibliographies of Interest to the Atomic Energy Program: Classified and Unclassified Versions, Monthly List of Bibliographies in the Atomic Energy Program. U.S.A.E.C. Technical Information Service Extension, Nuclear Science Abstracts.