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 research and development report details activities of the Irradiation Processing Department during the month of August 1965.

This report discusses research and engineering operations at the Hanford production reactors.

We are pleased to enclose copies of our Work Statement and Cost Estimate as a subproject to your program to nondestructively inspect the fuels on your NASA-Lewis contract. This confirms our telephone call and teletype of November 19, 1965 from Mr. Chockie to you. As we understand, the duration of this agreement should extend over the next six or nine months and will probably include the inspection of one or two fuel elements singly; later on, three batches of five elements. Accordingly, we recommend that the program be established for a period of nine (9) months with an appropriation of $10,430, including the fixed fee of $660. The attached Estimated Costs sheets show estimated costs for inspection of one fuel element at one time and five fuel elements are one time. This estimate is on a CPFF best effort basis calling for the application of tests developed on our present NASA-Lewis program. No additional development costs are included in this program. Shipping of fuel elements between Columbus and Northwest to be prepared by Columbus.

Process and Reactor Development progress includes depleted uranium irradiation in the B and KE reactors and thoria irradiation in the B, C, D, KE, and KW reactors. Reactor Engineering reports on higher graphite temperature tests, graphite strength tests, heat removal requirements following reactor shutdown, and reactor deactivation. Reactor Physics topics include: E-Q loading, test facility loss of coolant protection, ball 3X replacement, and in-core flux monitors. Radiological Engineering reports on radiation control experience, classification, radiation occurrences, effluent activity data, radiation standards and controls and procedures, and dose rates in the DR reactor block. Also listed are many revised standards issued during the report period. Operational Physics Operations report on pile physics plant assistance for the B, C, D, DR, F, H, KE, AND KW reactors. Process Physics studies include reactivity and control studies and product related studies.

Brief summaries are given for the status of activities in the following areas: Reactor fuels; Reactor engineering; Reactor physics; Radiological engineering; Process standards; Process change authorization; Fuel failure experience; Pile physics assistance; Process physics studies; Testing of fuel elements; and Testing and irradiation services.

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Considerable technology has developed for production of tritium in metallic target systems. At normal N-Reactor temperatures ({approximately} 300{degrees}C), aluminum-lithium alloys appear to offer a satisfactory system for tritium production. However, reactor safety requirements have generated interest in a target system which will hold the lithium in place at temperatures to 1200{degrees}C. At the same time, gas retention at irradiation temperatures ({approximately}300{degrees}C) must be acceptable, and extraction of the product must be practical. To determine in-reactor gas release characteristics of the silicate and aluminate materials, targets were irradiated in quartz and aluminum capsules. Following irradiation, the gas (condensible and noncondensible fractions) released in-reactor was recovered by drilling the capsules. Subsequently, the targets were recovered and heated in a laboratory vacuum system to investigate characteristics of tritium and helium evolution as a function of temperature. The experimental procedures are discussed briefly, with details in the Appendix. The results of the study are discussed in terms of in-reactor release and later in terms of laboratory extractions.

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