Abstract: A stainless steel clad 9-rod assembly fabricated by The Babcock & Wilcox Company was irradiated in a boiling water loop of the General Electric Test Reactor. A post-irradiation examination revealed no significant dimensional changes on the fuel rods. the results of mass spectrometric analysis made of the pelletized UO2 fuel indicated a maximum burnup of 11,500 MWD/tonne was attained by Rod B-4 during the exposure.An x-ray diffraction examination of an unirradiated fuel sample revealed the presence of UN2 and U2N3 phases. Metallographic examination of the irradiated microstructures revealed similar second-phase particles.

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

From introduction: "This article describes a training aid that was at the Ames Laboratory in order to give the plant protection group of the Laboratory an opportunity to practice closed chest cardiac massage on a simulated model. Details of the model are given so that professional or semi-professional people who may be faced with a sudden emergency requiring immediate action may duplicate this training aid."

This technical report outlines the results and characteristics of the reactions of gallium (I) salts in aqueous bases. This report also details experimental results.

From abstract: "The adsorption of ethane, ethylene and acetylene on clean iridium in a field emission microscope has been found to cause characteristic changes in the work function of the iridium surface. Further changes, which are time and temperature dependent, result when such surfaces are heated. Flash filament experiments have shown that the changes in work function upon heating are due to desorption reactions and that the desorbed product consists principally of hydrogen. By assuming a linear relationship between surface coverage and work function, it has been possible to determine the desorption kinetics from the observed rates of work function change at various temperatures. The results are consistent with a mechanism involving stepwise surface dehydrogenation in which a pair of hydrogen atoms is removed from the hydrocarbon molecule in each step, followed by desoption of the adsorbed hydrogen. At very high temperatures the remaining carbon atoms are removed, presumably by evaporation."

Abstract: The removal of both SM-1 Core I high burnup elements from SM-1 Core II and the insertion of the PM-1-M-2 element and the SM-1 Core I spare element in SM-1 Core II is discussed. Nuclear and thermal characteristics of Core II with these changes are presented and conclusions related to the changes in the hazard potential are made. If the core change indicated by this report is made, local peaking factors will be decreased and burnout ratios will be increased. This, of course, in itself leads to a more conservative estimate of core safety. There is no conceivable reason why the perturbation may not be safely made in the SM-1 Core II.

Abstract: A control system to provide digital printing and to plot an analog trace on an electric operated IBM model 11C Output Writer is described. The Digital mode of operation translates multidigit numbers through a set of commands to print each digit serially, then presents them to the output writer in a time sequence. The Analog mode of operation converts a d.c. input voltage to a digital number and by tab and space bar commands translates the carriage horizontally a distance proportional to this number.

The fabrication, irradiation and evaluation of the first two superheat fuel assemblies is described in detail. Experimental data indicate that, in general, the nuclear superheat fuel elements have performed satisfactorily under the testing conditions used. Certain problem areas which will influence future fuel element designs have been defined.

From foreword: This report presents the preliminary design of a gamma irradiator intended for use as an experimental hospital sterilizer.

The purpose of the test was to observe the extent and location of corrosion, crud deposits and defects in components of the primary fluid system and its auxiliaries. This observation will allow an estimate to be made of the future behavior of the affected parts. The test also provides for obtaining corrosion products and crud samples for analysis as necessary for planning remedial actions. This test was limited to the 1D Main Coolant Pump which failed November 3, 1958. The pump failed after 2234 hours of operation on "fast" speed and 887 hours at "slow" speed. An inspection for corrosion was not conducted but smear samples were taken and a radiochemical analysis made. This analysis showed the following isotopes were present in the smear sample: Co38, Co60, Fe59, Mn54, Hf191 and Zr95. The upper and lower radial pump bearings and journals were severely scored and galled while the thrust bearing and runner appear to be in good condition.

The purpose of the test was to obtain performance data for the main coolant pumps on fast and slow speed at various coolant temperatures. The 1A, 1B and 1C pump performances on both fast and slow speed were approximately as shown in the manufacture's predicted performance curve. The 1D pump performance was below the manufacturer's predicted flow efficiency, line current and hydraulic horsepower on both fast and slow speeds.

Abstract: During March 1958, representatives of the health and Safety Laboratory, New York Operations Office, visited Columbia University to make stray radiation measurement at the Van de Graff accelerator. A radiation survey was performed at the Van de Graaff electrostatic generator at Columbia University. The survey results do not indicate a particular need for additional shielding at this time. It is recommended that the analyzer area of the beam room should not be occupied during beam operations and the present interlock system should be modified by the installation of a photocell interlock as shown on the included plan.

Introduction: This report is principally concerned with analysis of measurements taken on the APPR-1 core during the course of the extended Zero Power Experiments (ZPE-2). The bulk of these measurements are reported in APAE No. 21. There are some additional measurements reported in APAE Memo 115. In addition to the analysis of the ZPE-2 data some re-evaluation has been made of a few of the results obtained from the first set of Zero Power Experiments (ZPE-1). The ZPE-1 measurements are reported in APAE No. 8. During the course of analysis work it became apparent that a considerable amount of basic experimental data had been taken on the APPR-1 core. It seemed worthwhile to organize this report in such a fashion that other investigators could make maximum use of this data. It provides excellent opportunity for individuals and groups interested in basic reactor reactor analysis problems to check calculational techniques. An attempt has been made to include all of the fundamental information concerning the material content and geometry of the APPR-1. This material is in included in the Appendices. In addition, cross-section files and group constants have been listed rather extensively in order that other investigators could compare results presented in …

"Formulas are given to express the general particle trajectory and the equilibrium orbit for a slightly disturbed synchrotron in terms of the amplitude and phase functions for the ideal machine. If these functions are known, orbit computations can be carried out by simple integration procedures. The formalism is expected to be useful especially for considerations such as beam alignment or generation of an external electron beam. Some equations given earlier are repeated for completeness."

Introduction: In September of 156, Gilbert Associates, Inc., entered into a contract with the United States of America, acting through the United States Atomic Energy Commission, for the study and preliminary design of a nuclear power plant being considered for integration into a central station power system at an overseas site.

Abstract: Napier Drilling Company of Dallas, Texas drilled 53,998.0 feet for exploration purposes, under Contract No. AT(05-1)-256. This footage was drilled in 508 holes during the period from June 21, 1954 through May 13, 1955.

From abstract: "On the 86-inch cyclotron a 41-kw beam has been calorimetered at a net ion loading efficiency of 40%; the average proton current was 1.85 ma at 22.5 Mev. Practical specific yields have been determined for (p,2n) reactions on zinc and bismuth. The investigation of products of proton-induced fission of uranium has been continued and new techniques are being used in measuring angular distribution of reaction products. The 63-inch heavy particle cyclotron is now in operation; N+++ particles have been accelerated to ~25 Mev. In preliminary tests, induced activities have been detected in carbon, nitrogen, and oxygen targets. A hot-cathode ion source is ready for test operation. The 22-inch cyclotron is being used in an investigation of the problems associated with the use of rf and dc electrodes for the acceleration of protons from the ion source into the dees. Radiation-induced corrosion in Inconel tubing containing #21 eutectic (ANP) has been produced by proton irradiation in the 86-inch cylclotron; it is shown that the corrosion was not due to thermal effects. Approximately 150 grams of highly purified U 238 (< 5 ppm U 235) have been prepared, and two grams of thorium 230 (ionium) has been enriched to 90.6%."

Abstract: Chemical and physical data on twenty binary uranium compounds that may prove suitable for refractory nuclear fuels were assembled. The compounds were those with aluminum, boron, carbon, iron, nickel, nitrogen, silicon, or sulfur. Too little is known at this time about the compounds to evaluate any of them for fuel. The program is being extended in an effort to provide the needed data.

A simple method of solving for the phase shifts of the pion-proton scattering is presented. The rapid solution afforded can be utilized, as the Ashkin diagrams have been employed, to give starting values to an electronic computer or alternatively to analyze with more ease the variation of the phase shifts as a function of the input data in terms of the coefficients of the angular distributions. A new plot of a function of the total cross section versus the pion energy is introduced. The nearly straight line resulting should help to evaluate the experimental data.

Abstract: A low-level airborne radiometric survey of the younger pre-Cambrian Dripping Spring quartzite, undertaken in the mountainous region lying roughly 100 riles east of Phoenix, was completed June 3, 1955. Twenty-seven radioactive anomalies were located. To date seven of these have produced uranium ore, four more will probably become producers, and six others may possibly become producers. Flying was concentrated in the Dripping Spring quartzite, but reconnaissance flights were made over other formations. Private prospecting, both from the air and on the ground, increased considerably when the airborne project started. Eleven of the private discoveries have produced ore, and many others show considerable promise.

The error that results when it is attempted to evaluate stress from a reading taken on a single element SR-4 strain gage in a biaxial stress field is discussed. A method is presented for relating SR-4 rosette strain gage readings directly to the biaxial stress state without the necessity of first converting strain gage readings to true strains. Correction formulas are presented for use when single element SR-4 gages are used as rosette elements or as stress gages.

A preliminary mathematical study is made of the maximum expected expansion of barium titanate ceramic. It is noted that there is insufficient physical evidence for a complete answer and some possible mathematical models are discussed and compared.

When a one-half ounce spherical charge of high explosive is detonated over a flat plane bounded by a 5 degree incline, the type of phenomenon encountered depends on the distance from ground zero to a beginning of the incline. If this distance is 48" the wave assumes a smooth contour on the plane. Detailed investigation of the shock velocity above the plane reveals that there is a pressure gradient along the shock front for a considerable region which replaces the usual triple point.

"In order to determine the factors involved in the scale-up of cores with concentric inlet and outlet pipes, a 48 inch carbon steel flow model, geometrically similar to a 6 foot diameter core, has been assembled and tested...Visual studies were made of dye and gas behavior in the sphere, and quantitative measurements of point residence times were obtained through the use of conductivity cells actuating a Brush recorder. Static pressure drop across the core was measured."