Annual report submitted by the Girl Scouts of the United States of America to Congress describing highlights from 1964, activities, organizational leadership, and other information about scouting programs.

Report discussing the possibility of a future investment in Talisman Sugar Corporation. The report includes a letter summarizing the report from R. W. Bowman to C. L. Huston, Jr., Talisman Sugar financial documents, the United States Sugar Corporation's statement of income, and the South Puerto Rico Sugar Company's balance sheet.

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.

The analysis of the thermal and hydraulic characteristics of the heat rejection system of the Tower Shield Facility (TSF) experiment is presented. Among the subjects discussed here in considerable detail are the convective and radiative heat rejection capability of the heat exchanger, NaK circulation around the system loop or driven by a SNAP 2 thermoelectric pump or natural circulation, and temperature distribution throughout the system both in transient and steady-state conditions.

A study was made of the deformational behavior (creep) of pillars made from three quasi-plastic rock--salt, trona, and potash ore. The first phase of this study considers the design of a model pillar suitable for creep tests; in the second phase, six model pillars were prepared from salt from two sources, from trona, and from potash ore. The pillars in each group were subjected to a different but constant axial stress, and the axial strain was measured for 1,000 hours. An analysis of the data shows that in general the creep rate for these model pillars can be expressed by the relationship .epsilon = K/sub 1/ sigma/sub 0//sup n/, where .epsilon is the strain rate, sigma/sub 0/ is the applied stress, and K/sub 1/ and n are constants. For the rocks included in this test, n ranged from 2.4 to 3.3.

A review of the nuclear safety aspects of a proposal to process about 150 to 250 tons of thorium containing about one kilogram U-233 per ton has been made. The review was made at the request of the Chemical Processing Department in whose Purex plant the thorium processing will be carried out. The review group finds that the proposed operation can be conducted with no more risk of criticality than attends the standard plutonium processing in Purex, provided the safeguards planned by the Department are carried out. The review group also has developed some suggestions by which the Chemical Processing Department could enhance its nuclear safety position in all its processing of fissionable materials. These suggestions take the form of hazards analysis procedure additions and formalization and interpretation of criteria. These suggestions are not meant to imply that present operations in CPD are unsafe, but rather that a continuation of the past trend of upgrading safety is desirable in order to cope with more complex, dynamic and potentially more hazardous future operations.

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This report covers the period May 1, 1964, to May 1, 1965, since the last report submitted on May 1, 1964, and is the fifth annual report in the series. The "Scintillation Counter" was put into operation on May 10, 1961, and has been in satisfactory operation except for brief periods of down time for modification, repair, and maintenance.

This report is a guide for producing permuted indexes for personal files, annotated bibliographies and or the Ames Laboratory's annual progress reports.

An evaluation of Hanford reactor process water treatment practices was made in an effort to ascertain the reasons for variations in the effluent activity between reactors. Recommendations are made for improvements in unit processes as well as for the over-all treatment process based on field inspection of the water treatment plants. In addition, a research program is proposed to supplement the recommendations. The proposed research is designed to uncover methods of more efficient filtration as well as other procedures which might eventually lead to significant effluent activity reductions. The recommendations and research results will be applied toward process optimization.

This is an addendum to the unclassified document entitled, ``An Evaluation of Hanford Water Treatment Practices.`` All classified data pertinent to the above document have been included here for reference. Data tables include chlorine demand (1964); chlorine contact times for reactor areas; calculation of flocculation; flow velocity in flocculation basins; overflow velocity; and particle removal efficiency; and filtration and backwash flow rates.

This report discusses research and development programs of the Irradiation Processing Department in FY-1965.

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.

This report details activities of Battelle Pacific Northwest Laboratory as compiled by the department managers for the month of December 1965.

This test was performed to investigate the effects of increased reactor flow upon the downcomer pressures and water levels. Recent theoretical studies had confirmed earlier ones that indicated a relatively weak downcomer approach box structure with an allowable working pressure of 4 psig. Since a flooded approach box would yield pressures in excess of 4 psig on the lower approach box plates and since downcomer flows approaching the flooding point were planned, experimental values of the downcomer pressures as the reactor flaw is increased were obtained. The initial test results indicated that concern was justified. Therefore, under Design Change {number_sign}1052, the approach box walls were stiffened to withstand a working pressure of 10 psig and a maximum allowable pressure of 15 Psig, In addition minor modifications were made to the approach box baffling and to the downcomer orifice plate, Additional test results were obtained after the completion of this design change with still further increases in reactor flow. However, only about 40 per cent of the planned reactor flow increase was attained. Further flow increases will be delayed several months until the completion of the thoria irradiation program. Therefore, this interim report summarizes the test results to date and discusses …

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

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This report covers the activities with regard to on-site customer irradiations as of February 13, 1965. The report covers the status of material undergoing irradiation, awaiting disposition, material shipped during the month, and current status of all reactor test holes.

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This report provides a review of the KE Downcomer development test, model data from the K-Downcomer tests, and a discussion of cavitation and bubble formation in nearly saturated water flow.

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