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Heating distributions have been obtained for the SNAP 10A reactor by means of a thermal paint technique in the Rhodes and Bloxsom 60 in. hypersonic wind tunnel. Data and correlations are presented only for those reactor components where the ratio of the local heat transfer to that on the stagnation point of the calibration sphere was found to be independent of tunnel conditions. It is shown that these heating distributions can be applied directly to reentry conditions provided the thermally painted and the bare reactor surfaces are both catalytic to atom recombination.

This report for December 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; and weapons manufacturing operation.

Programs undertaken by N-Fuels Engineering should be designed to achieve the following general objectives; (1) maintain and/or improve fuel element quality level necessary to assure satisfactory reactor performance; (2) develop the fuel fabrication technology required to support the development and testing of new fuel designs; (3) reduce fuel manufacturing costs to achieve projected operated cost targets; (4) reduce the uranium metal costs charged to N-Reactor. Further, these programs must be integrated to provide maximum support to identifiable Section and Department goals. The specific goals for CY-65 are: (1) development technology necessary to support conversion to co-product operation early in CY-66; (2) conduct a program of uranium fabrication development to improve fuel element quality and reduce uranium costs; (3) improve fuel element quality, manufacturing yields, and conversion costs for the current production fuel design; (4) develop fuels capable of extended exposure and/or higher power level operation in support of alternate reactor operating plans; (5) develop new fuel fabrication techniques to extend the capabilities for fuel fabrication within the N-Reactor Department; (6) initiate equipment design and procurement actions as necessary to provide capability to meet production schedules.

Two half-plant tests were conducted at D reactor to evaluate the effect of process water pH on corrosion of aluminum process tubes and fuel elements. The first test demonstrated that a reduction in coolant pH from 7.0 to 6.6 reduced aluminum corrosion by a factor of between 2 and 3. Fuel weight loss data from the second test indicated that reducing coolant pH from 6.6 to 6.2 would result in an additional factor of 2 to 3 reduction in aluminum corrosion. This report presents the results of ex-reactor process tube measurements an thermocouple probe annular temperature measurements made on six new process tubes irradiated during the second test. These results were combined with similar data obtained from six new process tubes irradiated during the first test. The combined results were used to estimate the effect 7.0, 6.6, and 6.2 pH on corrosion of aluminum process tubes.

Data in this report are significant to Pile Physics calculations and are submitted by the Area Physicists at the respective reactors. Reactivity in non-uranium charges and in radial and spike enrichment is calculated either by one-group diffusion theory as described in HW-60439, or by the simpler flux-squared weighting method. The former method provides a more accurate evaluation for larger enrichment inventories; the latter method is sufficient for radial enrichment of less than about 0.25 per cent excess K.

This document provides the reactor daily reports for January 1, 1965 through December 31, 1965. (FI)

This report provides the status of production test control tube loadings in reactor process tubes containing significant amounts of SS materials.

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The following subjects are discussed: areas of ''normal'' geothermal gradient, large areas of higher-than-''normal'' geothermal gradient, hot spring areas, hydrothermal systems of composite type, general problems of utilization, and domestic and world resources of geothermal energy. Almost all estimates and measurements of total heat flow published through 1962 for hot spring areas of the world are tabulated. (MHR)

The Bureau of Mines determined agents that are effective in foaming heavy brines and oil from gas wells in severe concentrations of sodium chloride, in severe concentrations of calcium chloride, or in moderate oil-brine mixtures. Dynamic tests were designed to select the more effective foaming agents. Numerous foaming agents were tested in concentrated simulated brines, in oilfield brines having varied concentrations of ions, in heavy natural brines, and in a commercial brine generally used as a reservoir pressure-balancing fluid. Several agents were detected that could perform efficiently in the field under the most severe saline conditions. Agents that promote foaming in oil-brine mixtures were also determined.

This report continues the tabulation of reactor effluent data for record purposes. During this report period, al reactor coolant had sodium dichromate added to a concentration of 1.0 ppm. coolant for both of the K Reactors was treated with liquid alum at a rate of about 12 ppm. Bauxite was used at all other reactors to provide a nominal alum concentration of 18 ppm during treatment. The coolant pH at DR, F, KE, and KW was reduced from 7.0 to 6.6 on October 23, October 29, December 5, and December 6, 1964, respectively. By the end of the report period, pH 6.6 coolant was in use at all reactors.

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This report describes some Sandia tests performed in the Martin Company 200-kilowatt hyperthermal arc-powered tunnel.

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Declassified 4 Sep 1973. Information on the development of the 710 Reactor is presented concerning the performance testing of refractory-metal fuel elements, critical experiment mockup of 710 Reactor, reactor component design and development, and test facilities and pilot loop design. (DCC)

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