ABS> The removal rates of iron, nickel, and chromium from synthetic stainless steel waste solutions during electrolysis over a mercury cathode were studied. The loading capacity of the mercury for the stainless steel metals was estimated on the basis of laboratory experiments to be about two% by weight. The laboratory data indicated that, at an electrode potential of --1.80 voits vs S.C.E., 85 ampere-hours per liter of waste removed essentially all of the stainless steel ions from a sulfuric acid solution containing 0.13M metal ions at 35 deg C. (auth)

The conditions under which hydrogen could be quantitatively recovered from mixtures of gases by oxidation over fixed beds of CuO were investigated. The conversion of H/sub 2/ to H/sub 2/O by reduction of CuO in fixed beds increased with in- creasing bed length, temperature, hydrogen/argon ratio, and decreasing mesh size of CuO. Residence times required for 99% conversion in a 1- in.-diam. bed were 0.6 and 1.2 sec for 30% hydrogen-70% argon and 10% hydrogen90% argon mixtures, respectively, at a total gas flow of 1 l/min. The CuO used was 25-mil-diam. wires with a surface area of 0.019 m/sup 2//g. The residence time required for a given value of conversion decreased about 10% when the total flow rate was increased from 1 to 1.7 liters/min, which indicates that the reduction is mass-transfer controlled to a slight extent under the experimental conditions used. (auth)

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

Experimental work consisted of one new run started and completed this quarter, and the completion of one of the three continuing runs. Of the scheduled operating time, the beam was on for 69.4% of the time, 2.3% of the time was used for experimental setup, and equipment outage took 29.3% of the time. There were two scheduled and two impromptu shutdowns. During one of the scheduled shutdowns the external-beam extraction magnets were installed in the east and south tangent tanks. The other scheduled shutdown was to readjust the Bevatron magnet elevation to correct for foundation subsidence. Internal magnets were also installed. In the new linac development program the ion source was run at 480 kv with a beam current of 100 ma. The linac tank was partially deplated to provide a clean copper surface, and welds and holes were plated with copper. The r-f losses were thereby reduced 20%. (auth)

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The average energy release per fission event in a reactor is dependent on the composition and arrangement of the lattice materials. In a study of heat generation in the NPR, Nilson developed expressions for calculating the average energy released in each material per fission event. These relationships have been used in the present calculations to obtain the energy release per fission in existing Hanford reactors.

The discharge of radioactivity from Hanford production reactors to the Columbia River has been studied for a number of years. The primary purposes of these studied have been to learn of the factors influencing production reactor effluent radioactivity concentrations and to develop methods for lowering the discharge concentrations of these radionuclides. In 1962 the Coolant Systems Development Operation (CSDO) began work on this program to determine the in-reactor film compositions and the inventory of radionuclides held in these films with the long-term objective of learning more about the complex in-reactor retention reactions that influence radionuclide effluent concentrations.

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Experiments to obtain detailed thermal flux distribution measurements within a unit fuel cell and measurements of sub-cadmium and epi-cadmium U/sup 238/ absorption in the fuel rods are described. These quantities are required for determination of the thermal utilization and resonance escape probability of the fuel loading. (auth)

The purpose of this document is to summarize the status of the current non-uniform aluminum corrosion program. Also included are justifications for and descriptions of program activities which could continue through FY-1971.

A 40-day uranium core canning test (10,000 lbs of high nickel AlSi) is proposed in which one canning line has only AlSi of 0.78-1.1 % Ni added as makeup; the other canning lines would be operated as usual. Besides monitoring the Ni content and other impurities in the test and control lines, attributes, variables, and destructive fuel element data would be collected and analyzed. Estimates for annual savings are given for 8, 9, and 10-line shifts per day.

A process was developed for separating promethium from raixed fisBion product rare earths by continuous multistage conntercurrent extraction with 100% tri-nbutylphosphste from nitric acid of 12 N or higher concentration. Distribution coefficients at 12 N acidity for aecdamium. promethium. and samarium are 0.43. 0.82, and 1.55, respectively. Single-stage separation factors of 1.9 between successive elements can be maintained throughout the system to give separations dependent only on the number of stages. Extracted values can be recovered from the organic solution by stripping with a smaller volume of dilute nitric acid. A flowsheet for purification of promethium includes one cycle for separation of promethium from neodymum and lighter elements and a secondycle for removal of samarium and heavier elements. Each cycle consists of a series of countercurrent partitioning stages. followed by stripping stages and an evaporator. With 20 stages in the first cycle and 34 stages in the second, a 90% yield of promethium with a purity of 83% can be obtained from a typical mixture of fission product rare earths, assuming essentially perfect mechanical efficiency. An increase to 34 stages in the first cycle would permit a 93% yield of 99% promethium. (auth)

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The multiple hydroclone system removed l83 grams of corrosion product solids in l814 hours of operation during reactor run 2l. The low removal rate was attributed to plugging of multiclone feed ports that presumably occurred during the latter part of run 20. After modifications to the reactor core and removal of the multiclone unit at the end of run 21, the reactor core was backflushed with the flow direction in the core loop reversed. During this period, the single hydroclone removed 205 grams of solids in 10.5 hours of operation. (auth)