The test established that a practical orifice selecting device can be made and used to control the water flow rate to a process tube at either of two accurately calibrated rates with no loss of accuracy in flow measurement. With the selector tested, there was no flow restriction during the orifice transition. The pressure fluctuations during the change were small in magnitude, and caused no operational problem. The test demonstrated that orifice selection is feasible from operating other factors justify their use.

Major additions to separations facilities may be required because of increased reactor power levels, reduced exposures; changes in slug specifications, obsolescence of existing solvent extraction plants or development of new separations processes with lower operating costs. The magnitude of first costs for a separations plant is so large as to discourage production planning which would require an additional major separations facility. Experience in separations design has shown that certain process and equipment changes, if they could be developed, would significantly reduce the capital investment in a separations facility. Accordingly design development for a new separations facility is under way. The purposes of this document are to present the results of the first separation design study directed toward a new solvent extraction plant and to summarize process, plant, and equipment changes which should be developed to achieve significant capital and operating cost reduction.

At HAPO the protection of employees from nuclear radiations has paralleled or preceded the emphasis on atomic products production. The production of atomic products on the scale for which HAPO was designed presented voluminous problems in employee education, radiation detection, shielding, and indeed, fundamental research to determine working limits for the various types of radiation exposure which would necessarily be encountered, and to determine working limits for the deposition of radioactive isotopes and mixtures of isotopes in the human body. Since the time radioactive materials first arrived at HAPO and the start-up of the first HAPO reactor on February 23, 1944, there has been a fundamental philosophy that all employee exposure to nuclear radiations should be maintained at a minimum, as opposed to just some level of exposure below the accepted permissible limit. It was with this philosophy in mind that the many achievements and advances in the science of radiation protection at HAPO have been forthcoming. These advances in radiation protection ar discussed in this report.

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The purpose of this report is to present a semi-quantitative discussion of the effect of the heat capacity of the process tube assembly on the outlet water temperature following a mild inadequate cooling incident involving an entire reactor.

This is the monthly report for the Hanford Laboratories Operation, August, 1959. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology financial activities, visits, biology operation, physics and instrumentation research, employee relations, and operations research and synthesis operation are discussed.

A study has been made to determine the adequacy of the KER-1 loop emergency dump valve in protecting the fuel elements against damage during a loop casualty. In a functional test of the radiation trip procedure of the KER-1 loop during a reactor outage, it was found that the indicated process water flow was much lower than expected. Subsequent inspection of the emergency dump valve showed that the dump port was considerably blocked with rust and scale, creating a flow restriction. As it was thought that inadequate cooling water flow could result if a similar situation occurred when the reactor was at normal power levels, a study was made of the loop and the adequacy of the valve to handle casualties.

This document defines the basic criteria to be used in the preparation of detailed design for Project CG-558, Reactor Plant Modification for Increased Production and for Project CG-600, 100-C Area Alterations. It has been determined that the most economical method of increasing plutonium production within the next five years is by the modernization and improvement of the 100-B, 100-C, 100-D, 100-DR, 100-F, and 100-H reactor plants. These reactors are currently incapable of operating at their maximum potential power levels because of a limited availability of process cooling water. As a result of this program, it is estimated that 1650-2350 megawatts of total additional production will be achieved.

Certain laboratory processes require low-powered radio-frequency heating with fine continuous control. A lightweight low-powered induction heater which is capable of delivering about 20 watts of power into a load 12 feet from the heater with fair efficiency was developed to meet this need.

Work on the present relativistic electron bunching accelerator (S-band rebatron) is concerned with improving the electron bunching, current and beam focusing, and the design of a portable prototype system. Most of the parts for this new machine were fabricated and tested and the construction initiated. A photograph showing the present stage of construction is given. Since an S-band rebatron cannot be scaled directly to X-band, a lower voltage Xband rebatron, followed by a short section of a linear accelerator could solve the problera. An Electronics Associates analog computer was received and is being programmed to explore the design problems. The numerical work of evaluating the TM and TE modes of teflon dielectric cavities is largely completed. New ideas and further modifications are being tried in Si crystal harmonic multipliers for use as sources for testing components. The new klystrons now being used permit driving the crystals harder, and hence improve the harmonic power. (For preceding period see AECU-3535.) (M.H.R.)

Costs are estimated for the production of uranium and pure thorium from monazite concentrates. The process involves; reaction of the monazite with caustic soda, dissolution of the hydrous oxides in hydrochloric acid, separation from the bulk of the rare earths by hydroxide precipitation of thorium and uranium, and purification by solvent extraction. (auth)

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>The materials problems associated with the present sodium graphite reactor system have generally been approached by using existing knowledge and data to meet the proposed operating conditions. This discussion reviews the general reactor concept and the specific materials used for the major reactor components: (1) shielding materials; (2) core materials; and (3) sodium cooling system materials. In each case, the materials problems and the materials used to minimize or eliminate these problems are described. Economical nuclear power is currently dependent on the flow of improved materials for high temperature use in high radiation fields. Rapid progress is being made in this respect. (auth)

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The desigm and analysis of a mechanical transition joint between materials having different thermal coefficients of expansion are discussed. The analytical treatment is based primarily on the analysis of short cylinders. The specific desigm for the Zircaloy-2stainless steel core vessel joint in the HRT is discussed in detail. Brief summaries of preliminary designs and test results are included along with results obtained from the tests performed on the final design for the HRT. (auth)

A design study is presented for a sodium cooled, graphite moderated power reactor utilizing low enrichment uranium fuel. The design is characterized by dependence on existing technology and the use of standard, or nearly standard, components. The reactor has a nominal rating of 167 thermal megawatts, and a plant comprising three such reactors for a total output of 500 thermal megawatts is described. Sodium in a secondary, non-radioactive, circulation system carries the heat to a steam generator at 910 deg F and is returned at 420 deg F. Steam conditions at the turbine throttle are 600 psig and 825 deg F. Cost of the complete reactor power plant, consisting of the three reactors and one 150- megawatt turbogenerator, is estimated to be approximately ,165,000. (auth)

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Thermal neutron spectra were measured with timeof-flight techniques. Spectra were obtained for pure water and for a nearly homogeneous subcritical assembly where the ratio of themal absorption to high energy scattering cross section was t 125, 150, 175 0.3. For each medium, spectra were measured at 298 and 586 K. The experimental results are presented and compared with calculated theoretical spectra The agreement between theory and experiment is excellent for the multiplying media. On the basis of this agreement, one concludes that chemical binding effects in light water play a negligible role in determining the equllibrium neutron spectrum in water assemblies. (auth)

Separate abstracts have been prepared on the papers presented at this conference. (C. H.)

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A compilation of 290 references on gas bearings is presented. In most cases an English resume' of each reference is included a translation being made when required. The references are arranged alphabetically by first author. Indexes included are the year of origin corporate author, subject, patent number, and country of origin. (J.R.D.)