One of the major unsolved problems affecting the life of the SNAP II Power Conversion System is the mass transfer of corrosion products by mercury and subsequent deposition. It is feared that the corrosion products might tend to accumulate in critical areas such as orifices, bearings and so forth. Therefore, this test was conducted to evaluate a corrosion product separator and to determine the influence of corrosion product removal on corrosion rate. The corrosion product separator was successful in removing 85 percent of the elements corroded from the container walls. The loop and separator, both fabricated from Haynes alloy No. 25, operated for 1000 hours. The mercury was boiled and condensed at 1100 deg F, superheated to 1190 deg F and subcooled to 325 deg F. The flow rate in this loop was much higher than in previous loops, being approximately 37 pounds of mercury per hour as contrasted with approximately l2 pounds of raercury per hour. No increase in corrosion rate was noticed as a result of the higher flow rates and velocity or by the removal of corrosion products. If this type of separator or an improved type works equally as well in the final application, the danger …

Second part of the "final report of a study directed toward the evolution, design, and demonstration of the principle design features of interim indirect cycle water cooled and moderated nuclear power plants which will be useful in early cooperative programs between the Atomic Energy Commission and the United States maritime industry" (p. II-i).

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Progress in fuels and materials development is summarized. Major areas of investigation include a materials study by means of sample fuel plates containing uranium alloys or cermets, burnable poisons, non-uniform fuel and poison distributions and clad with various aluminum alloys; and an engineering study of fuel element geometries optimized in heat transfer, hydraulics, and materials strength. Up to 45 wt% U-Al alloys, 6 to 65 wt% UO/-Al and U3O6-Al dispersions, including enrichments ranging from 20% to 93%, were tested to 70% burnup in de-ionized water at 200 deg F in the MTR. Their performance at higher temperature is still being investigated. Test results for the MTR conditions indicate that all of the compositions investigated to date will successfully withstand even the longest irradiation at these conditions if properly fabricated. Some high strength aluminum alloy claddings, not yet fully tested, show some peculiar surface effects which may be related to corrosion. Metallographic studies of irradiated cermets reveal a reaction'' (diffusion) zone produced around UO/sub 2/ particles in contact with aluminum. These zones are being studied by means of x-ray diffraction, electron microscopy, and electron microprobe analysis. From engineering studies has come promise of improved heat removal and lower pumping requlrements for …

Wax lap preparation for the vibratory polisher consists of melting the wax, pouring it into the bowl, and allowing it to solidify. The wax adheres to the bowl without difficulty. Specimens to be polished were mounted in bakelite or lucite. Grooves formed in the surface of the way can be removed by melting with hot water. (R.J.S.)

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The Argonne Thermal Source Reactor is a highly enriched, light-water- moderated thermal reactor. Movable shielding allows complete access to one face of the core. There is ready access to the central and 2 peripheral core locations, and it is possible to thrust samples with small reactivity effects into these locations. The reactor was approved for operation at 10 kw. Design and construction details are described to aid present and potential users of this facility. (auth)

A description is given of a method suitable for the automatic solution of certain optimum design problems on a digital computer for cases where the number of constraints imposed on the design is not greater than the number of design variables. The problem is transformed to one requiring the minimization or maximization of an unconstrained function, for which a gradient method is used.

Technical report describing "A means for automatically determining the coordinates of a point at the center of a bubble chamber track." from the abstract.

From Object and Scope of This Paper: "This paper describes the apparatus and procedures used at the National Bureau of Standards for the measurement of d-c resistance when an accuracy of a few parts in a million is required. The object will be to explain procedures in detail and as simply as possible, with a minimum reference to theory."

This manual presents the operating instructions and necessary background information to safely operate the Chemical Steam Generator provided by Thiokol Chemical Corporation for Aerojet General Corporation, REON Division.

Engineering studies of a 6-in.-ID countercurrent foam column were started. The capacity of Mark II Stacked Clone Contactor was found to be limited by gradually increasing entrainment. Thoria sols were prepared from trough denitrator products in a conical bottom tank agitated by circulation through an external centrifugal pump. Experimental results agreed favorably with predicted results for the reaction of CO with CuO and fur the simultaneous reactions of H/ sub 2/ and CO with CuO. In a 2-in. dissolver, Modified Zirflex dissolution rates of Zircaloy-2 increased non-linearly with F/S. The 250-ton prototype shear was received and installed. Priorities were established for development work on graphite fuels. A total of 5 SR Core I fuel clusters were mechanically dejacketed from the second carrier shipment of SRE Core I fuel. Degradation of NaK to a solid or waxy form required that the slugs be ejected by the jackscrew. The NaK disposal system operated satisfactorily for the Iast ~3000 ml of NaK. A procedure for estimating the temperature rise of spent reactor fuels during shipping gives reasonably good results. A puIse column was operated with the light phase c nt-nuous using an external phase separator. Zirconium ates were dissolved by HF in molten …

A comparison of methods of capital cost estimation used for nuclear fuel reprocessing plants shows that, because of the special nature and complexity of such plants, cost estimation methods for conventional chemical plants involving the use of cost factors are not applicable and will give low estimates. Cost factors which are available from other countries where reprocessing plants are installed should be used with caution since those factors apply only for the particular design philosophy used and pertain to industrial conditions which are different in this county. Capital cost estimation methods involving direct take-offs from detailed design drawings are necessary to obtain reliable estimates. The methods of estimating operating costs for nuclear reprocessing and conventional chemical plants are similar.

Criteria for the conceptual design of the proposed Thorium Fuel Cycle Development Facility to be located at the Oak Ridge National Laboratory were established and are presented. In addition, conceptual layouts of the building and equipment are included. Reference fuel elements and processes that were selected as a basis for developing criteria for the facility are described. (auth)

Monthly newsletter of the High Plains Underground Water Conservation District No. 1, discussing the field of underground water. Topics include profiles of water conservation research, annual pre-plant soil moisture survey data, annual Winter Water Level measurement data, and information about the latest water conservation tips.

Report containing information regarding the demineralization of water via carbon electrodes. Includes steps taken in the experiment, advancements made in the types of carbon material used, and cost estimates.

A thermal flowmeter was designed and tested which will measure a wide range of flow rates for highly corrosive gases. Response to flow rate changes is fast. The pararaeters for changing the size and response to the flowmeter were evaluated. (auth)

Report concerning the study of multiple designs of solar distillers with the goal of increasing the fresh water ouptut.

Major effort during the report period was directed toward the in-pile testing program. Component PuO/sub 2/ and UO/sub 2/ powder blending trials were continued along with coprecipitated powder characterization studies. Arrangements for irradiation of short exposure rabbit capsules were made. (J.R.D.)

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Results are presented of a study concerning EBWR core designs in which uniformly enriched UC/sub 2/ fuel rods clad with Zr, capable of a maximum exposure at about 10,000 Mwd/t were used. Three core designs are described and nuclear constants and burnups characteristics are given. The third design (C), embodying improvements from cores A and B, demonstrated a more uniform radial fluid flow distribution and a greater Pu formation than in design B. The calculated maximum-to-average power ratio in design C and 2.1 which is nearly 1/2 of that in design A, and 3/4 of that in design B. (auth)

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A study was made to determine the effect of changes in natural uranium cost and in separative work charges on fuel cycle costs in nuclear power plants. Reactors considered were a Dresden-type boiling water reactor (BWR) and a Yankee- type pressurized water reactor (PWR), with net power ratings of 100, 300, and 500 Mwe. Fuel cycle costs were calculated for these reactors, using either enriched uranium or U/sup 235/-thorium as the fuel material. The price schedule for uranium was based on a feed material cost of /kg uranium as UF/sub 6/ and separative work costs of /kg uranium (Schedule B) and /kg uranium (Schedule C). The present AEC price schedule for enriched uranium was also used for purposes of a reference case. The results indicate that a reduction in present enriched uranium price to that given by Schedule B would reduce fuel cycle costs for the BWR plants by 0.4 to 0.5 mill/kwh for the enriched-uranium cycle, and 0.4 to 0.7 mill/kwh for the thorium cycle. Reductions in fuel cycle costs for the PWR plants were 0.5 to 0.7 and 0.4 to 0.75 mill/kwh, respectively, for the same situations. (auth)

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