Process development personnel have been seeking means of improving the (after thermal exposure) adhesion of the S8DR ceramic coating to chromized Hastelloy N tubing. This effort has led to the incorporation of an elevated temperature chromium diffusion treatment prior to the application of the ceramic coating. This report describes the results of tests performed to ascertain the influence of the additional thermal treatment on the 1400/sup 0/F creep-rupture properties of S8DR tubing.

Reactor water leaks cause outage time for locating and eliminating the leaks and for repairing damage paused by the vater that enters the reactor. The justification for equipment and process changes necessary for reducing the number of leaks and the resultant outage time is dependent on the number of leaks expected. This document presents an estimate of the future reactor water leak frequency and the average outage time charged to each leak. A water leak is defined as any entry of vater into the reactor moderator during operation. Future vater leaks are expected to result primarily from Van Stone flange failures and miscellaneous causes such as mechanical damage, fuel ruptures, and transverse cracks. It is assumed that continuous emphasis will be placed on corrosion monitoring to determine the tubes that must be replaced to prevent leaks because of internal and external corrosion. The number of water leaks is expected to average between 80 and 100 per year in the future. The normal-range of the number of leaks probably will be between 60 and 120 per year as a result of normal variation in the process tube physical condition. The number of outage hours charged per leak is expected to continue …

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 State Treasurer is authorized to accept certain unclaimed funds under the provisions of Article 4.08 Texas Insurance Code.

The research and development activities reported on are: enriched fuel (1.25% U{sup 235}), flex 2 code development, Pu burning and recycle, single tube fuel element, heavy isotope production, U{sup 233} -- Th{sup 232} fuel cycle, physics input for economic studies, Pu{sup 240} effective resonance integral, N-Reactor operator certification lectures, bases for control and nuclear instrumentation, and shield evaluation. (GHH)

A primary factor in assessing the impact on the biosphere of the discharge of heated reactor effluent to the Columbia River is the degree of initial dilution. Each of the reactor effluent lines discharges at the bottom of the river, approximately normal to the current, and near the main channel. As part of the Division of Production research and development program titled ``The Effects of Reactor Effluent on the Quality of Columbia River Water,`` the temperature measurements recorded in this document were taken over a period of several years. Generally, the exact locations of the ends of the effluent lines could not be determined from the river. The intent therefore was to determine the initial degree of dilution at the point where the mixed effluent first reached the surface, the so-called ``bubble,`` over a range of river flow-rates. A secondary goal was to determine the distance downstream (in quarter-mile increments) at which vertical mixing of the effluent streams could be considered complete. The data reported here have been partially reported previously and used in the development of a mathematical model of plume development. The purpose of this document is to provide a record of the field data in more detail …

This report discusses The Causes of Urban Violence: Selected Articles.

This report addresses the semiannual progress report for the period ending on February 15, 1963.

It is the purpose of this report to present data obtained from the routine reactor effluent radioactivity monitoring program as well as the results obtained from the research and development program directed toward the reduction of effluent radioactivity.

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