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Research progress is reported on solid-state theory, crystal physics, metals, nonmetals, radiation metallurgy, and reactor materials. Separate abstracts were prepared for each topic. (M.C.G.)

The thermal decomposition of ferric nitrate nonahydrate, chromium nitrate nonahydrate, aluminum nitrate nonahydrate, and nickel nitrate hexahydrate as well as the mw- tures of these compounds in the proportions produced in the dissolution of Nichrome and stainless steel alloys was investigated. The experiments were conducted in air at two heating rates, approximately 1.1 deg C and 2.6 deg C per minute. The intermediate producte and final products were analyzed by x-ray diffraction and chemically where it was appropriate. (auth)

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Work was carried out to obtain significant data on reactor excursions, in particular the SL-1 excursion, to extend the analysis of reactor transient behavior so as to obtain an improved understanding of the thermal and mechanical processes that take place during and following a reactor excursion, and to obtain chemical, metallurgical, and nuclear data relative to the pre-accident performance of the SL-1. Laboratory investigations were made of samples of the SL-1 power plant. Results are given and their significance discussed. An attempt was made to construct a mathematical model of reactor excursions, based partly on fundamental thermodynamic and nuclear considerations, and using some empirical results. This model was applied to SPERT and BORAX excursions with some success. Recommendations concerning reactor design and operation, which have arisen from the SL-1 accident and its analysis, are summarized. Results are presented in tables and graphs. (M.C.G.)

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.

When the pulse from a parallel plate electrode ionization chamber containing an attaching gas is examined with a linear pulse amplifier having the proper integration and differentiation time constants, the pulse height is an anslytic function of the attachment coefficient and the electron drift velocity. The expressions for the pulse height as a function of the partial pressure of the attaching gas, electron drift velocity, attachment coefficient, chamber geometry, and amplifier time constants are evaluated and presented in tabular form. (auth)

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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 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.

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.

The M-101 (an all steel) shipping container and safety cage was in use for about 15 years for transporting and storage of enriched U. With slight modifications and the addition of an inner container, the M-101 can be used to ship Pu metal. Various physical tests performed on the M-101 and inner container are described, and critical array sizes under various conditions of spacing and flooding are discussed. (auth)

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This memorandum outlines the area of interest in connection with the SSBN launch application, on modification of the Tory II-C control rod system; and suggest a plan of development of information. Because of the very limited space for overall missile length, little room is available for control rod motion upstream from the core. Shortening the rod stroke, and the total length occupied by control rod mechanism., becomes very desirable. Changes in the actuator and linkage mechanism will clearly help, and should be investigated. However, this is concerned only with neutronic aspects.

The inelastic interactions of negative pi mesons with protons at 374, 417, and 454 Mev incident pi kinetic energy are studied by measuring the differential distributions of finalstate neutrons. The pi source is an internal target of the Berkeley 184-inch synchrocyclotron. A magnetic beamtransport system momentum-anaiyzes and focuses the pi beam at a liquid hydrogen target located in an adjacent shielded experimental area. The time-of- flight distribution of neutral particles is measured at various laboratorysystem angles between 10 and 65 deg. Neutral particles are detected by observing the charged products of their interactions in plastic scintillator. The time-of- flight information is determined electronically by time-to-height conversion and pulse-height analysis. The time resolution of the total system is 1.0 nsec. Detected neutral particles accompanied by charged particles are separated by the electronic system from those not accompanied by charged particles. Analysis presuming the principal inelastic reactions to be pi /sup -/p yields pi /sup +/ pi /sup -/n and pi /sup -/p yields pi /sup 0/ pi /sup 0/n separates the time-of-flight spectra into gamma rays, neutrons from the reaction pi /sup -/p yields pi /sup 0/n, and inelastic neutrons. Calculated values of the neutron- detection efficiency are used in the …

An experimental program to evaluate the performance of FCR and EFCR fuel during transient operation is outlined, and the initial series of tests are described in some detail. Test results from five experiments in the TREAT reactor, using 1-in. OD SS-clad UO/sub 2/ fuel specimens, are compared with regard to fuel temperatures, mechanical integrity, and post-irradiation appearance. Incipient fuel pin failure limits for transients are identified with maximum fuel temperatures in the range of 7000 deg F. Multiple transient damage to the cladding is likely for transients above the melting point of the fuel. (auth)

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.

Technical progress in specific reactor projects and in general engineering research and development is reported. The information is presented in five main sections for each of which a separate abstract was prepared. (J.R.D.)

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