Several of the plutonium assay methods were reexamined as part of a continuing effort to make improvements in these frequently used analyses. This investigation included a study of the controlled-potential coulometric, amperometric, potentiometric, and photometric titration methods and their applications to assays of delta-stabilized and alpha plutonium metal.

The Chase two-dimensional analyzer is a 64 channel by 64 channel analyzer with a magnetic drum memory and a buffered storage system. The memory capacity is 2 counts per channel. The maximum storage rate is limited by the drum speed and is about 800 counts per second for a featureless spectrum.

The isotopes of lutecium were used to measure the neutron temperatures in two collimated beans of neutrons emerging from HIFAR>

A survey of the aqueous coordination chemistry of beryllium is given. The possible use of coordination chemistry in the separation of beryllium from fission products is discussed, outlining methods for separation processes.

From Abstract : "The mechanism of the reactions of the halates, bromate, chlorate, and iodate, with dichromate in fused alkali nitrates has been shown to involve a fast equilibrium followed by a slow rate determining strip to give oxygen and halogen gases as final products." Experiments outlined serve as insight into the structure of fused salts or fused electrolytes.

Technical report. From Abstract : "The determination of the crystal structure of bis(meta-chlorobenzoyl)-methane was undertaken by x-ray methods in an effort to clarify the ambiguous position of the hydrogen atom on the enolic form of β - diketones and hence in intramolecular hydrogen bonds."

The nature and types of internal molecular and thermal motions that polymer chains and polymer segments undergo have a great bearing on the physical behavior of polymeric solids. A relatively new tool is now available that permits us to observe and study internal thermally-induced motions directly at the atomic or molecular level rather than from macroscopic observations. this tool is nuclear magnetic resonance spectroscopy. This talk discusses (1) the nature of nuclear magnetic resonance, (2) NMR line shapes and the influence of temperature, (3) NMR line widths and second moments as a function of temperature, and (4) lists six general conclusions.

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This report summarizes the technical progress on the subject contract for the period September 15 to November 14 1962.

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 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.

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.

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- …