The flowsheet proposed by KAPL for the treatment of alkaline nitrate radiochemical processing waste has been modified to include an ion-exchange step for the decontamination of cesium, strontium, and other cationic fission products. In laboratory studies of the electrolysis steps in a nitrate reduction cell, synthetic alkaline waste, 0.55 to 4.83 M total electrolyte, was decontaminated from ruthenium by factors of > 210. The nitrate of 3.0 M waste was reduced to ammonia with current efficiencies of 100%. Power consumption was 4.7 kwh/lb of nitrate reduced. Significant factors affecting the rate of ruthenium decontamination were temperature, cathode area, cathode current density, and electrolyte concentration. Those affecting nitrate reduction current efficiencies were the cathode current density, electrolyte concentration, and stirring rate. In an acid-base membrane cell, reusable nitric acid as well as sodium hydroxide was regenerated. However, such a cell is less economical to construct and operate than the nitrate reduction cell. At least 5 kwh of power is required to transfer 1 lb of nitrate from ORNL type waste. In addition, the greater complexity of the acid-base cell makes it less adaptable for remote control.

This document details activities of the irradiation processing department during the month of August, 1958. A general summary is included at the start of the report, after which the report is divided into the following sections: Research and Engineering Operations; Production and Reactor Operations; Facilities Engineering Operation; Employee Relations Operation; and Financial Operation.

The primary purpose of this test was to demonstrate that the inside of a rear-cross-header, its nozzles and pigtails could be decontaminated by recirculating for 30 minutes, a 60{degrees} C, O.3 pH chromic acid solution. Secondary purposes were, (1) to determine the magnitude of radiation increase in piping and acid equipment external to the reactor encountered during the test and (2) to obtain information as to the kind and amount of contaminants removed by the acid solution.

It was the purpose of this talk to present up-to-date information with regards to dimensional stabilityof metallic uranium. A brief discusssion concerning the history, present status, proposed theories, and recent results are given. The factors affecting and methods of minimizing dimension changes are outlined.

High energy p-p scattering has been interpreted by several authors in terms of highly singular noncentral interactions. The triplet state calculations were carried out in the Born approximation and, together with the singlet, yielded an almost isotropic (c.m. system) differential cross section. Agreement with experiment was good at large angles but the theoretical peak in the forward direction, due mostly to singlet d scattering, was too large. It is not clear however that the Born approximation should be valid for singular potentials.

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Techniques were devised for quantitatively determining the accuracy of potentiometric uranium analyses in uranium-aluminum alloys containing up to 55 wt. % U and for evaluatin; the segregation existing in uraniumaluminum alloys containing as low as 7 wt. % U and as high as 50 wt. % U. A theory for predicting the mode of uranium segrcgation in these alloys was postulated. On the basis of the observed uranium segregation, the uranium content of a hypothetical fuel element was predicted by means of several sampling schemes. Dip sampling of the melt was demonstrated to be satisfactory for alloys containing 7 to 19 wt. % U. However, this technique was not considered suitable for alloys containiog 40 to 50 wt. % U, because a significant number of samples is required from the casting or the wrought alloy to adequately represent the fuel content. (auth) An accurate and rapid method for the volumetric determination of uranium has been developed for the ranges 0.3% to 90% uranium. The existing mercury cathode deposition equipment has been modified for the rapid removal of metallic impurities and for the electrolytic reduction of the uranium. (auth)

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During the period from May 1957 to July 1958, four nuclear batiery powered timers were fabricated and tested from two basic designs in the time ranges of onesecond, three-second, annd half-hour intervals. The timers were temperature-tested over a range of -65 to +165 F with accuracics over this temperature range from plus or minus 10 perceat to plus or minus 15 percent. Each unit has a volume of 10 cubic inches, and the timer can be initiated either by an explosive squib or a pull-out wire. At the end of the timing interval, the timer has ann output of 30,000 ergs. The cost of the program was ,000. From the results of this development program, it appears quite feasible to build operable nuclear battery powered timers on a production basis. (auth)

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Because of wide variations in the venturi throat pressure, well beyond the panellit gage trip range, that occur during the sequence of operational charge-discharge, the panellit gage cannot be included in the scram safety circuit during the period of time that charge- discharge operations are being performed. In its stead, the function of the panellit gage is replaced in an overlapping manner by a tube inlet pressure monitor that is equipped with high and low pressure trip mechanisms that may be included in the scram safety circuit during the time that the panellit gage must be by-passed. The tube inlet pressure monitor is then used to provide the protection from unstable flow that is normally obtained with the panellit gage. This memorandum describes the manner in which the tube inlet pressure monitor trip points are to be determined and used.

At 11:20 A.M. Tuesday, July 24, 1951, a radium capsule containing 49.6 milligrams of radium became open to the atmosphere t the Kelley-Koett instrument Company, 930 York Street, Cincinnati, Ohio. This radium was contained in a platinum tube and was used for the purpose of calibrating radiation detection instruments. At the time of the accident, the actual chemical composition of the radium salt was not known. On Tuesday morning, July 31, 1951, Mr. W.A. Bigler and Mr. R.A. Miller of the Monsanto Chemical Company, Mound Laboratory, Miamisburg, ohio were sent to the Kelley-Koett Instrument Company for the purpose of recovering as much of the radium as possible and to help in the reduction of the health hazard. This paper details the activities undertaken to survey and decontaminate the area.

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