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.

This is the summary report on the ARF Project C 127, entitled "Preliminary Studies Related to Radioactive Fallout", covering the period from April 1, 1959, to April 29, 1960.

Abstract: "The accuracies which can be achieved in analog recording systems are for the most part tape limited. While reasonable variations in tape speed do not directly affect the accuracy, such variations result in improper tape tensioning, which in turn results in poor head-to-tape contact. The quality of the tape transport mechanism should be such that the error introduced by improper head- to tape contact is less than tape errors. Some additional equipment is necessary in setting up a tape recorder for a given experiment. The amplitude of the input pulse spectura to the recorder should be adjusted for optimum value and, if possible, the counting rate should be adjusted to obtain good tape utilization. An oscilloscope is probably adequate to satisfy both conditions."

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

From introduction: This report has been prepared to present the details of the heavy water cooled power reactors, including cost estimates, plant design studies, and other work directly related to the current status of D2O reactors.

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.

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).

From foreword: The purpose of this conceptual design is to outline criteria for the selection and development of a reactor plant with a fossil fuel fired superheater, a conventional generator plant and auxilary systems constituting a complete operating unit capable of producing a gross electrical power output of 22,000 kw.

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

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.

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.

From abstract: The principal efforts during the fourth project quarter were the near-completion of the final design and preparation of specifications for plant components. Reactor development work included final preparations for the flexible zero-power test (PMZ-1) program and revised fuel element irradiation test program, continuation of reactor flow test, further work on heat transfer test program, and final design and fabrication of the prototype magnetic jack-type control rod actuators.

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

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.

Abstract. A fast-slow coincidence scintillation spectrometer for gamma-gamma cascade measurements following thermal neutron absorption in nuclei is now in operation at the Livermore 1-megawatt pool-type reactor. Design features of the spectrometer and experimental techniques in its use are discussed with particular emphasis on the application of the recently introduced sum-coincidence method for analysis of capture-gamma double cascades. A new technique for the determination of added neutron binding energy is presented and various types of coincidence data from appropriate experiments are illustrated.

Abstract. An inexpensive method for detection of dust-loaded high efficiency filters is described. Air flow is continuously indicated by elementary pitot tubes and plastic rotameters. Accuracy obtained is within +- 15%. Information as to construction, installation, and use is presented.

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.

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.

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."

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."

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."

Summary: Prototype testing of the safety and control rod drives indicated that both units functioned properly. No major problems were encountered during testing. Seal leakage data collected indicated that the seal units were performing satisfactorily. Scram times during both cold and hot testing were excellent and actually better than expected.

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.