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This report presents the dose rates which were observed during the removal of a Zircaloy-2 process tube from C Reactor. The corresponding calculated activity is also presented for the purpose of correlation with the observed dose rate. The tube was removed on July 22, 1964, after having been irradiated by a neutron flux for 560 days (based on time operated efficiency). The tube activity was monitored with a super high range TP (0-5000 R/hr) by suspending a probe through an access port in the floor of the ``D`` machinery room. As tube 3353 was pushed and cut into sections, the highest activity observed was 675 R/hr, which was seen in the center three-foot segment. The corresponding calculated activity was 650 R/hr. The neutron flux profile, as shown by tube activities along its length, was extremely peaked in the center; for example, the area under the activity curve was less than one-third of the area under a cosine curve of the same amplitude and cycle length.

This is the monthly report for the Hanford Laboratories Operation, July 1964. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, physics and instrumentation research, applied mathematics, programming operation, and radiation protection are discussed.

A summary of HAPO activities is given to include separate sections on the N-Reactor and other current production reactors. Specific programs and fuel performance for current production reactor fuels is discussed. Also, the production status, fuel performance, development program and process technology for N-Reactor fuels is presented.

Reactor support charge designs and patterns have been numerous and varied over the past few years, the basis for acceptance of a particular support loading being determined from a consideration of fabrication costs and the hydraulic characteristics of the proposed dummy load as it applies to a particular reactor. Since the first three or four dummy pieces downstream of the fuel column (and upstream of the column in a spline tube) are discarded after the irradiation process, it is desirable to use tubular dummies for this portion of the support charge which are less expensive to fabricate and which are easily identified during the charging-discharging process. However, there exists a remote possibility that one or more tubular pieces could be inadvertently placed in a rear nozzle resulting in a flow restriction in the process tube. These arrangements of tubular support pieces in the dummy pattern, i.e., tubulars positioned against the fuel column and/or in the process tube rear nozzles, have been hydraulically tested to determine if there is adequate and unrestricted flow at normal operating header pressures.

The release of uncontrollable quantities of harmful fission products such as I{sub 131} upon processing areas. At present this is done by procedural techniques using cards, filing techniques, and cross checks. These methods are entirely independent of the characteristics of the fuel itself and are subject to failure from human error. It is therefore advantageous to find a method of determining the age of irradiated fuel after discharge from the properties of the fuel. Such a method, with its relative immunity to human error, would be very useful in checking shipments as well as for such jobs as determining the correct age of fuel being stored for accumulation of desirable fission product daughters. It was the purpose of this effort to make a study of possible methods of direct fuel age determination, formulate and perform a test of the most promising method, and analyze the results in terms of practicability here at Hanford.

This report, for July 1964 from the Chemical Processing Department at HAPO, discusses the following: Production operation; Purex and Redox operation; Finished products operation; maintenance; Financial operations; facilities engineering; research; employee relations; weapons manufacturing operation; and safety and security.

Reference 1 gave mixer recommendations for aluminum spline tubes at the K reactors. On completion of the study, R. F. Corlett requested a more detailed economic study of mixer useage at KW reactor. R. G. Clough also requested additional information on use of mixer elements in fringe tubes. In order to answer these requests, additional information was needed and requested. A. W. Medcalf replied giving enriched metal requirements in support of mixers. No other information vas received so it was not possible to make the economic study requested by R. F. Corlett. This report presents more detail on tube-life estimates associated with use of the eccentric and concentric-wall tube designs in central- and fringe-zones and the results of five downstream thermcouple probes that operated in concentric-wall tubes at KW reactor. Also, modification of the concentric-wall tube (milling down of the ribs) is discussed.

This production test authorizes the irradiation of full length charges of solid aluminum in the KER loops while on single-pass operation with process water cooling. Calculations show that the irradiations will not result in any foreseen reactor or personnel hazards and can be safely performed in the KER facilities.

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This report is an inventory record of materials which were received and shipped from the Purex Process during this time period. Material accounting includes uranium, uranium-235, plutonium, and other transuranics.

To satisfy reactor coolant supply criteria requires a knowledge of available emergency flow rates from secondary and last-ditch systems. This document presents a method for calculating high-tank flow contribution to the last-ditch coolant system from routine high tank-high velocity flush data. The measured flush flow is converted to equivalent through-reactor flow at 20 C and at the critical time of high-tank takeover from flywheel decay.

Figures are given.

The purpose of this test was to evaluate the behavior of natural lithium-bearing materials and to provide samples for production and extraction information. Testing of the target elements was done in conjunction with a test evaluating the behavior of NIEl fuel elements. Conditions for operation during the test were similar to, or more severe, than conditions expected in N Reactor.

The AEC has indicated a need for plutonium with a high concentration of the Pu-240 isotope. Concentrations up to 25 W/o Pu-240 have been requested with a firm commitment given for 25 kilograms of plutonium with at least 18 W/o Pu-240. To meet this production demand, irradiation of depleted uranium, 0.22 W/o U-235, will be undertaken. This test authorizes half of the irradiation in a Hanford K reactor, outlines the general plans, and presents the details of the irradiation. The objective of this test is to authorize irradiation of approximately 12 tons of depleted uranium, 0.22 W/o U-235, in a Hanford K reactor. The depleted uranium will be irradiated to exposures which will yield plutonium with at least 18 W/o Pu-240, an average exposure of approximately 1600 MWD/T.

The attached tables are an extension of the data that will be used in the forthcoming Production Studies. It considers thorium load substitution for the natural uranium cases previously reported. The power level, operating efficiency, exposure, conversion ratios, tonnage, and production are given for the natural U loading, blanket loading, and full conversion. The small reactors, the C reactor, and the K reactor are considered.

Investigation of several alternative methods of modifying the C- Reactor overbore test facility in order to terminate the production tests has been completed. The results are presented in this report.

This document defines the objectives, bases, and functional requirements that shall govern the preparation of design of the coolant backup system for three remaining smaller reactors. This project will increase the reliability of the coolant backup facility at B Area by providing an independent last-ditch coolant system to B and C Reactors. The reliability of the last-ditch system for D Reactor will also be improved in that the present F and H leg of the export system will no longer be a part of the new export system.

Reactor phase-out discharge planning involves forcing all tubes into a discharge pattern such that they can all be discharged at the appointed time with maximum fuel utilization. When considering reactors operating on the block discharge concept, action must be taken early to cause the fringe to reach goal exposure at the same times as the central core. For the case of alternate row or random discharge of core material, there is the additional problem of discharging all core tubes at a single outage without greatly underexposing or overexposing either of the discrete batches involved.

The objective of this test is to evaluate the effects of oil quenching, alpha annealing, and an Al-Si braze pre-canning treatment on the irradiation behavior of hot-die-sized fuel elements.

Large scale self-support fuel usage at the K Reactors began in mid-1963. With the advent of the new fuel element concept, self-support development work in different areas was required. One such area was that of the supports, or rails, used on the elements. The initial self-support rail design on the elements, in order to meet production commitments, was only slightly modified from previous test models. These rails were identified as ``bridge rails.`` Development of the self-supports has continued and the first major modification, the ``arch-rails,`` of the original design is now ready for reactor testing.

This document reports the IPD production projections and reactor inventories for Hanford C and K reactors. Tables included contains the following information: Operating efficiency, exposure, conversion ratio, tonnage, production, and power level.

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