Brazing alloys such as 48 Ti-48 Zr-4 Be (wt%) and 49 Ti-49 Cu-2 Be (wt%) have been found to readily flow on oxide and graphite ceramics. Two demonstrati on fuel element assemblies were fabricated to illustrate the usefulness of these procedures for nuclear applications. One of these assemblies contained graphite tubes and end caps which were brazed to a molybdenum hanger. The second demonstration fuel element was composed of a compartmented aluminum oxide plate to which aluminum oxide cover plates were brazed. (R.J.S.)

The scintillation response of CsI(Tl) crystals, having various thallium contents, was measured for excitation of the crystals by monoenergetic gamma rays, protons, and alpha particles. The investi gation was made to provide a test of some of the features of a theoretical model of the scintillation process in thallium-activated alkali iodides proposed by Murray and Meyer. In order to insure that the results obtained in this program would provide a critical test of the scintillation model, special attention was paid to technical effects which could influence the interpretation of the experimental data. For example, the effect of the pulseanalysis time on the relative scintillation response of CsI(Tl) to various charged parti cles was investigated. In addition, the emission spectra of the CsI(Tl) crystals were measured for excitation by x rays, protons, and alpha particles. The results of the investigation showed that the scintillation efficiency of CsI(Tl) is a continuous function of dE/dx, as assumed in the scintillation model, within the accuracy of the experiments when the effect of delta ravs are considered. This led to the conclusion that the light output of CsI(Tl) crystals is, in general, a nonlinear function of the energy of the particle. The shape of the …

The purpose of this document is primarily to discuss the effects of current retubing programs on the graphite moderator of the K Reactors. A secondary purpose of this report is to present general information related to graphite arrangement and keying patterns at the other operating reactors and to review, in a limited way, the types of graphite distortion observed at these reactors.

This is the monthly report for the Hanford Laboratories Operation October 1962. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, physics and instrumentation research, operations research and synthesis, programming, and radiation protection operation are discussed.

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Because of the questionable performance of the 190-DR steam backup system during the power outage of April 6, 1962, it is felt that a general review of the DR secondary water system capabilities and the standby status of the pumping units is warranted. This report shall briefly describe the performance of the steam backup system during the April 6 power outage and the subsequent power outage of July 10, 1962. Since the former outage, tests have been conducted on the steam pump units to determine their capabilities; the test results are presented in this report. A statement of the generally accepted criteria for secondary coolant system adequacy is included and recommendations for meeting the criteria at DR reactor are presented.

Conclusions resulting from a recent corrosion study, together with evidence of graphite damage possibly occurring during retubing operations (having obvious implications in regard to reactor life), initiated a critical assessment of the water treatment process. This study was undertaken to determine whether immediate or near-term process changes could be made at the older reactors to minimize aluminum corrosion without causing adverse effects in other areas.

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This report, from the Chemical Processing Department at HAPO, for October, 1962 discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations; facilities engineering; research; employee relations; and weapons manufacturing operation.

This document is divided into the following sections: fuel element swelling model, tubular fuel element irradiations, and Zircaloy-2 cladding strain study.

The objective of this production test was to evaluate the irradiation behavior of N. Reactor fuel elements at conditions equivalent to or more severe than those expected in N Reactor. The thermocouple train consisted of eleven 23-inch NAE1 elements (replicas of an N Reactor fuel element) plus five 16-inch tubular perfs. The elements were enriched to 0.947 per cent. They were coextruded Zircaloy-2 jacketed self-supported uranium tubes concentrically nested one within the other to provide an element with four heat transfer surfaces and three coolant channels. For specific dimensions, refer to Production Test IP-477-A.

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The purpose of this document is to present the latest results of a continuing instrumentation study being conducted by Research and Engineering. In a previous report results of 1-and 6-node calculations, for percentage- and fixed temperature-trip instrumentation were presented. These results were used to obtain a general understanding of the problem and to assess the value of using a multinodal approach. Calculations to determine the amount of protection provided by linear rate and period instrumentation were not performed at that time. Thus, the results of this previous report are limited in that they cover only a part of the possible nuclear safety instrumentation. The previous results indicated that the multinodal approach should be used in analyzing high level and intermediate instrumentation. The results presented in this report were obtained from an 11-node model covering percentage- and fixed-temperature-trip instrumentation, and also linear temperature rate-of-rise and linear power rate-of-rise. Other specialized cases were also investigated. In particular, data were obtained to provide: Eleven-node results for the old reactors; Results for the K reactors comparable to those previously obtained for the old reactors, and results using parameters chosen for the high speed scanner project; Linear power-rate-of-rise at the high levels. Comparison between 6- …

This document provides details of activities of the Fuels Preparation Department during the month of October 1962. (IF)

A long term study designed to determine the biological effects of daily Sr{sup 90} ingestion in miniature swine has been underway in this laboratory since 1958. The Ultimate objective of this study is to provide data that will assist in defining for man the levels of dietary Sr{sup 90} at which there is no damage or negligible damage to him or his progeny. The animals being used in these studies are miniature swine which have a mature weight of 60 to 80 kg. The dietary requirements, gastrointestinal tract, and bone mass of miniature swine are quite similar to man. These factors, along with a relatively long life span, dictated their use in this study.

This document presents the Westinghouse Astronuclear Laboratory contribution to the RIFT flight safety review. While the presented herein is the best data that exists at this time, it can not be considered the final data. In consideration of the extremely dynamic nature of the program , it is intended to issue periodic revisions reporting new developments in the Westinghouse program.

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A problem which frequently arises in experimentai heat transfer work is that of determining the surface temperature of a tube in which heat is generated electrically. Solution of this problem involves a temperature measurement of the opposite surface to which a correction factor, the temperature drop through the tube wall, must be applied. This temperature drop is obtnined through the solution of the diffurential equation governing the temperature distribution in the tube wall; however, in the case of temperature-dependent properties of thermal conductivity and electrical resistivity, the governing equation is nonlinear, which necessitates special solutions. In this study a hypothetical surface-temperature problem was established, and the solution of the governing nonlinear differential equation was accomplished by means of an electronic analog computer. Assuming variable properties, the example used in this study was that of a one-dimensional steadystate heat flow through both a thick- and a thin- walled tube. (auth)