This report covers the activities with regard to on-site customer irradiations as of the above date. The report covers the status of materials undergoing irradiation, awaiting disposition, material shipped during the month, and current status of all reactor test holes. The integrated exposure values are calculated in accordance with HW-62781, {open_quotes}Status Report Equations.{close_quotes} The integrated exposure reported is the average exposure received by the surrounding uranium columns. Conversion to exposure received by the sample is left to the customer.

This report details a K area test with the following objectives: find the temperature range within a graphite sample carrier; find the temperature range with a solid graphite bar; find the temperature range with a test hole; determine the temperature difference between the old and new graphite sample boats; compare the temperature of a sample load and a solid bar in the same location; and find the temperature range in which the graphite samples are irradiated in all test holes. Results and conclusions are presented.

This study was prepared in support of AEC-requested reactor case studies. Two of the cases include local separation and purification of tritium from Hanford irradiated aluminum-lithium alloyed slugs after 1974, at which time, the Savannah River Plant would be shut down. Consideration is given to processing N Reactor rods or {open_quotes}K{close_quotes} Reactor I&E slugs. Quantities of tritium to be produced would be five kilograms per year in one case and seven kilograms per year in the other case. The facility would process tritium only through the purification stage. At this point the material would be shipped offsite for storage, packaging and any future weapon stockpile rework.

This monthly report details research and development activities of the Irradiation Processing Department for the month of July 1965.

The scope of this report defies a concise abstract. In lieu of an abstract, the following topical outline will both indicate the subjects covered and show how these subjects are organized. Part I, Engineering Aspects: Blister Formation, Temperature Effects, Cooling Effects, Drive Connections, Housing Effects, Housing Materials, Radiation Effects. Part II, The Behavior of Boron Carbide-Aluminum Poisons: Swelling, Swelling Rates, Restraint, Material Behavior.

This annual report details activities of the Fuel Element Development Committee. A summary of Hanford Atomic Products Operation activities is provided along with programs and performance of K, small reactor, and N-Reactor fuels.

This specification covers the processing of a pilot lot of 2.4 w/o uranium oxide fuel in the N-Reactor Fuels facilities for the period from August 16, 1965, through March 1, 1966. A maximum of 180 fuel pieces will be processed. The fuel will be processed or stored in 306, 333, and 3,715 Buildings. Processing steps will include end closure welding, support and locking clip welding, final etching, autoclaving, final inspection, and assembly. Shipment to 100-N Area and from 325 Building are also covered.

This monthly report details research and engineering operations of the Irradiation Processing Department during the month of July 1965.

This monthly document details activities of the Battelle-Northwest Physics and Instruments Department during the month of July 1965. (FI)

This monthly report addresses developments in departmental organization, laboratory experience, environmental evaluation, nuclear safeguards, dosimetry studies, radiological development, environmental studies, and outside consultations.

The purpose of this document is to outline the proposed implementation of engineering program results to remedy the major horizontal control rod (HCR) problems at Hanford production reactors. K and C Reactors currently use a water cooled, round, aluminum control rod packed with boron carbide powder, B and D Reactors use a water cooled, flat, aluminum rod made up of sintered boron carbide-aluminum rings strung on three cooling tubes, all of which is encased in an outer aluminum shell. The nature of the problems -- progressing toward a limiting condition at a predictable rate -- lends itself well to a stepwise or ``as needed`` approach in applying a solution. Such an approach offers the dual benefits of realizing maximum reliable usage from each piece of equipment and of distributing the renovation costs over several years time. The specific program proposed herein emphasizes the immediate application phase.

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Hastelloy X wire wool has been considered by the Architect Engineer for exterior thermal insulation of some pipe sections of the ATR* gas loop. Heart transfer studies were made simulating gas loop operating conditions. This report describes the apparatus used and the resultant data. The insulation (manufactured by a commercial supplier) is of interest because of its corrosion resistance, strength, and ability to withstand impact and abrasion. Also, it is not a source of chlorides. The insulation is compressed and sintered to a given density and sinter bonded to a thin Inconel outer sheath.

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The Core Insulation Development Program was initiated to investigate characteristics of pyrotile insulation as to bow, structural integrity, and thermal gradient when subjected to reactor temperatures and bundling pressures. Other forms of core insulation were to be tested at they become available.

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