Information is presented on current reactor fuel development (uranium core production data, fuel performance, AlSi process development, and alternate process development) and NPR fuel development (fuel production status, KER loop testing, and process development).

This report is a compilation of available data on ruptures that have occurred since KER start-up. Some of the data presented in this report are inconclusive, but are reported to insure a complete summary of all potential and confirmed ruptures.

To run a second BPA outage test at the DR-Reactor using the same instrumentation and procedure but increasing the trip-out level fro 800 MW up to a maximum of 1200 MW.

This document discusses activities of the Fuels Preparation Department during the month of December 1961. (FI)

The technical basis and criteria for five requirements are presented. Requirement 1 is that the coproduct target element shall be compatible with the driver element in the environment of the N-Reactor primary loop. Requirement 2 is that the target element shall be compatible with nuclear safety requirements under all credible accident conditions. Requirement 3 is that the coproduct element shall be unmistakable from other fuel element models in use or expected to be in use during the period 1966-68. Requirement 4 is that the target element shall have a degree of reliability that is compatible with reactor performance objectives. Requirement 5 is that the target element shall be compatible with procedures for post-irradiation processing.

This report details planning to run a second outage test at the DR-Reactor using the same instrumentation and procedure as an earlier test but increasing the trip-out level from 800 MW up to a maximum of 1200 MW.

The SSA 100 program will compute the buildup and decay of SS materials, (gms Pu, U-235 burnout and uranium burnout) in fuel that has been irradiated in any of the Hanford reactors. The routine input data for the program are the IBM production records supplied by the Production Forecasting and Scheduling Operation. The purpose of this program is to compute and prepare an accurate accountabilty report with a minimum of manual effort. This can either be a report for fuel discharges from the reactors or a report of the entire month end reactor inventory. It is not the purpose of this report to describe in detail the data processing techniques used to provide the accountability reports, this will be left to the discretion of the SS Accountability Operation and the programer. The purpose of this report is to present (1) the technical methods that are fundamental to the program, (2) the necessary instructions that are necessary to make changes or include additional fuel data on the data tape and (3) the necessary instructions such that buildup and decay data can be obtained for fuel elements on a non-routine basis.

This report details activities of the N-Reactor Department during the month of December 1962.

A half-plant low alum water treatment began at F Reactor on January 16, 1963. The tests, which had been prompted by the analysis of ledge corrosion attack on fuel elements, will demonstrate whether or not high alum feed is responsible for increasing the frequency of ledge and groove corrosion attack on fuel element surfaces. The effect will be evaluated by comparing visual examination results obtained from the normal production fuel irradiated in process water treated with two different alum feed rates. Five 20-column fuel discharges, ten columns from each side of the reactors have been taken during the test as follows: One discharge prior to the start of the test; One discharge such that the test side was exposed to coolant treated with both high and low alum feed, and Three discharges under test conditions. This report discusses the results obtained from the fourth discharge under test conditions.

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The use of uranium mononitride as a nuclear fuel is being considered for a number of high temperature applications. In comparison with the most often applied high temperature fuels, UO2 and UC, one finds that UN has a combination of the high melting point of UO2 and the thermal conductivity and high uranium density of UC. However, interest in UN is often dampened by qualitative indications of its low thermal stability and by lack of experimental thermodynamic data. Is is the purpose of this study, therefore, to provide a quantitative measure of the thermal stability of UN and to establish some of its thermodynamic properties.

This report itemizes the irradiations performed by Testing and Irradiation Services for Battelle-Northwest. It lists the material being irradiated, awaiting disposition and material shipped during the report period.

This document details activities of the N-Reactor Department during the month of December 1963.

We consider the kinetic isotope effect in three center reactions of the type of A+BC→AB+C. Such model calculations are a good approximation to primary hydrogen isotope effects. For abstraction or transfer reactions, B becomes H, D, or T. The dynamics of the three storm system are calculated for a general quadratic potential, with the assumption that the potential energy is constant along the reaction coordinate (flat top barrier). This model system can be calculated in detail and serves to illustrate the relationship between kinetic isotope effect and chemical bonding in the transition state. The statistical mechanical part of the calculation can be carried out exactly within the framework transition state theory or in any one of a number of approximations. The γ bar method gives particularly good insight into the chemistry of the problem with a minimum of arithmetic.

Optical absorption and photoconductivity measurements have been made on single crystals of pure synthetic rutile (TiO2). Reactor irradiations at 70°C totaling 4.8 x 10 18 nvt fast and 1.69 x10 19 nvt slow did not produce any discernible optical absorption bands; however, the transmission decreased 5 percent at all wavelengths. Reactor irradiation induced a [illegible] five photoconduction peaks in the wavelength range 4200 to 14,000 A. In addition the photopeak at 4065 A (3.05 eV) was enhanced and there were drastic changes in the dependence of photocurrent with light intensity. Gamma-ray irradiations as large as 10 9 r do not change the conduction properties. The photocurrent is proportional to a power of the light intensity; the power range from 0.65 to 1.24, for the crystals described in this work. The photocurrent vs. voltage dependence is more complex.

There is but little known about the thermal process involving the dynamics and thermodynamics of the cycling liquid H2 in the chamber and those of the H2 fluid flow in the cooling coil as well as the geometrical characteristics of the chamber body. This the physical equations governing this process are involving so many variables that this analysis becomes rather complex even if simplifying assumptions are made. To those difficulties is added the ignorance even of an approximative expression for some physical quantities such as film heat transfer coefficients entering as major parameters the process equation.

The purpose of this report is to determine the amount of refrigeration capacity required to cool down the 80" bubble chamber from ambient temperature to liquid hydrogen temperature.

The undercarriage system is required for translating, rotating, and lifting the 450 ton magnet and bubble chamber assemblies so that it can be accurately positioned in the experimental proton beam of the synchrotron. The system must make provision for the two magnet sections to be separated for the purpose of adjustment and maintenance of internal components.

The following general description of the theory and operation of a bubble chamber is presented so that firms who are interested in fabricating components for the Brookhaven 80" chamber will have a better understanding of the design parameters associated with it. This understanding, coupled with the fabricator's knowledge of manufacturing techniques, should enable the fabricators to suggest solutions to manufacturing problems consistent with requirements for chamber operation. In an effort to increase knowledge of fundamental nuclear particles and their interactions at high energies, various types of detecting equipment have been developed. One of these detectors recently developed is the bubble chamber. While there are variations as to liquids used, expansion techniques, means of illumination, etc. the basic concepts upon which all bubble chambers operate are similar. Therefore, it will be sufficient in this report to consider only one specific type, that is a chamber using liquid hydrogen

Photocopy of a psychological test report regarding Jack Ruby's mental state and character. The report is largely illegible.

Criminal intelligence report which states that three vehicles were seen outside the home of Michael R. Paine and Ruth Paine. Marina Oswald was living with the Paines at the time that President Kennedy was assassinated.

Criminal intelligence report addressed to Captain W. P. Gannaway of the Special Service Bureau in Dallas, Texas. The report, which was submitted by detective W. S. Biggio, states that a letter from J. White of Long Beach, California is attached. In the letter, J. White expresses the belief that Oswald was not guilty.

Photocopy of a report of the preliminary diagnostic impression of Jack Ruby by Manfred S. Guttmacher, M. D.

Criminal intelligence report which states that three vehicles were seen outside the home of Michael R. Paine and Ruth Paine. Marina Oswald was living with the Paines at the time that President Kennedy was assassinated.