About 70,000 pictures of 2.45-GeV/c K{sup -}-p interactions have been obtained in the present 72-inch hydrogen bubble-chamber experiment. Approximately 24,000 events of all topologies except 1-, 2-, and 3-prong events have been measured, and 50% have been remeasured. They report here on a study of the production of known resonances in the reactions: (1) K{sup -} + p {yields} {Lambda} + {pi}{sup +} + {pi}{sup -}; (2) K{sup -} + p {yields} {Lambda} + {pi}{sup +} + {pi}{sup 0} + {pi}{sup -}. The cross section for production and number of events in reactions (1) and (2) are given in Table I.

The altitudes and times of ablation have been determined for the SNAP-10A, SS-316 vessel wall reentering under various conditions. The results are confined to one typical location on the reactor and to one typical reentry trajectory. The location is the side wall of the vessel and the trajectory is the one used in NAA-SR-8303.

This document details activities of the N-Reactor Department during the month of January 1964.

This report details activities of the N-Reactor Department during the month of April 1964.

Irradiation of thorium for the production of ``clean`` U-233 at HAPO began in CY 1963. Several small-scale tests, involving from gram-size quantities up to a few elements, were successfully conducted; the results from these tests, coupled with theoretical predictions, indicated the desirability of further investigation. The objectives of this test are to (1) authorize the irradiation of about two tons of thorium oxide target elements in central zone process tubes of KE Reactor, (2) determine the reactivity effects of an enriched uranium-thorium oxide (E-Q) loading in the K Reactors, (3) demonstrate the feasibility of using the K Reactors in production of ``clean`` U-233, (4) provide sufficient irradiated thoria material to permit demonstration of the chemical processing capabilities, and (5) obtain data from an extended irradiation of one column of thoria elements.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Waggoner Carr, regarding a legal question submitted for clarification: Sufficiency of applications for a local option election and related question.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Waggoner Carr, regarding a legal question submitted for clarification: Whether Article 10.03(3) V.C.S. requires a supplier to collect the tax on all special fuels delivered to statutorily defined dealers or users who are not bonded, or whether it requires the supplier to collect the tax only on deliveries made to dealers and users who are acting in the capacity of non-bonded dealers or non-bonded users as classified by Article 10.11(1), V.C.S. and related questions.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Waggoner Carr, regarding a legal question submitted for clarification: Sheriff’s responsibility in mental health cases.

Document issued by the Office of the Attorney General of Texas in Austin, Texas, providing an interpretation of Texas law. It provides the opinion of the Texas Attorney General, Waggoner Carr, regarding a legal question submitted for clarification: Whether the Motor Transportation Division of the Railroad Commission of Texas has jurisdiction to regulate the transportation of dead human bodies.

Highlights include production program and development program reviews at the Mallinckrodt Chemical Works, and production and development at the National Lead Company of Ohio. Activities at the Savannah River Plant are briefly discussed. General Electric at HAPO reports from the irradiation processing department and the N-Reactor department. The Hanford laboratories report on fuel element work.

None

This report is divided into: current reactor production fuels, N-RD production fuels, and reactor fuel development (N-Reactor, current reactor).

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.

Large scale self-support fuel usage at the K Reactors began in mid-1963. With the advent of the new fuel element concept, self-support development work in different areas was required. One such area was that of the supports, or rails, used on the elements. The initial self-support rail design on the elements, in order to meet production commitments, was only slightly modified from previous test models. These rails were identified as ``bridge rails.`` Development of the self-supports has continued and the first major modification, the ``arch-rails,`` of the original design is now ready for reactor testing.

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 details activities of the N-Reactor Department during the month of March 1964.

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

This document details activities of the N-Reactor Department during the month of June 1964.

The capability of calculating the close-in effects of the shock wave from an underground nuclear explosion has been demonstrated. Agreement was obtained between calculation and measurements using .a spherically symmetric, hydrodynamic, elastic-plastic code called SOC for the Hardhat event, a 5-kiloton nuclear detonation in granite. This capability is dependent upon having a more or less complete de scription of the elastic and dynamic properties of the materials involved. When this information is available, agreement within the limits of uncertainty of the measurements can be calculated for peak pressures, peak particle velocities, shock wave time of arrival, and pressure pulse shapes.

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.