This report discusses two methods used for experimental determination of the interfacial tension of an immisible aqueous-organic system where the density of the organic phase is less than that of the aqueous phase. The methods discussed are the falling drop method and the Donnan modification/rising drop method.

From abstract: "A comparison has been made of methods for producing Fe59 of higher specific activity than that obtainable by irradiating natural iron in the Clinton pile. Five processes have been considered, (1) irradiation of natural iron in the Hanford piles, (2) irradiation of enriched F58 in the Clinton and Hanford piles, (3) Szilard-Chalmers enrichment using ferrocyanides in the Clinton pile, (4) collection of recoils in a phase separable from the bulk of the iron, and (5) the Co59 (n,p) Fe59 reaction in the Clinton and Hanford piles."

Abstract. The preparation and properties of a new explosive, liquid over the range -65 degrees F to +165 degrees F, are presented. This explosive, called NTN, is a 5/1/1 mole ration of nitromethane, tetranitromethane, 1 -nitropropane. The sensitivity and stability of NTN meet military requirements.

The purpose of this investigation is to make a preliminary study and evaluation of the application of ultrasonic equipment and associated handling equipment to the problem of decontaminating reactor tube dummy pieces. Reactor Section is currently planning the construction of batch process nitric acid facilities for dummy decontamination. It was felt that use of ultrasonics together with a solution less corrosive than nitric acid might provide adequate decontamination at lower project cost than the presently proposed nitric acid facilities. This report gives the progress of the investigation to date.

Quarterly summary report of studies conducted through the Radiation Laboratory, University of California. Some results reported in the report may be of a preliminary or incomplete nature.

Internal-conversion coefficients may be thought of as consisting of two parts: a usually dominant part which depends only on the atomic number and the nuclear transition energy, and a usually small part depending explicitly on nuclear transition matrix elements. This latter part arises from the penetration of the converting atomic electrons within the transforming nucleus.

A previous report on this subject (Brookhaven National Laboratory, AGS Internal Report, ECR-4) described in detail the methods of measuring the injected and accelerated proton currents in the Brookhaven AGS up to May 1961. At that time the accelerated current was measured by extracting the bunch frequency component of the signal given by a pair of radial position observation electrodes. The injected current was also determined by the signal induced on a similar pair of radial position electrodes. Absolute values were then determined from machine parameters and a wire measurement of the electrode sensitivities. Linac currents, however, were measured with transformers, calibrated by putting known current pulses through a single turn loop. As described in ECR-4, a crude current transformer was placed on the AGS ring and cross-calibration measurements were carried out using a half turn injected beam. The pickup electrode value was then found to be about 10% higher than that given by the current transformer. This amount of disagreement was within the estimated accuracy of the measurements and calibrations used at that time.

The discovery of the vector meson which mediates the weak interactions, W,1 would be of extreme importance for weak interaction physics and for field theory in general. The W, if it exists, will be made in a variety of processes such as v+N →W+ + e- + N, or n- + P →W- + P, or, as studied in this note, P + P → D + W+. The W couples to leptons with a dimensionless constant [constant not transcribed] where G is the Feral constant defined t=so that [constant not transcribed]. Thus for [equation not transcribed] and the smallness of this constant is, evidently, what makes any of the above processes difficult to detect. The W may have a variety of decay modes.

The discharge of cooling water from the Hanford reactors introduce radioactive contaminants to the Columbia River. These materials may subsequently bring about exposure to human populations either through the direct use of the water for sanitary purposes or transfers of the radioisotopes into the food chains. It is therefore desirable to keep to a minimum the amounts of radioisotopes released to the river.

Separation processes for production of pure rare earth oxides in useful quantities are discussed. A review of applications of these oxides in the ceramic industry in production of glasses, glazes, porcelain enamels, refractories, abrasives, electronic ceramics, and nuclear ceramics is also presented. 46 references.

A system for concentrating uranyl nitrate solutions was designed and installed in the Thorex Pilot Plant. A total of 16,060 g of uranium was concentrated in the system in 68 batch runs. A total of 14,400 g total uranium (14.180 g U/sup 233/) was recovered as product suitable for shipment. Uranium loss to the evaporator condensate was 0.03% of the total uranium processed. The material balance across the system was 98.4%. The average concentration of uranium in the evaporator feed solution was 29 g/liter; the average concentration in the evaporated solution was 298 g U/liter and in the product solution was 199 g/liter. Radiation readings of bottles containing product solutions were taken with a hard-shell cutie pie immediately after each run, and these readings ranged from 35 to 1100 mr/hr. The radiation levels of the bottles of product solution shipped averaged 78 mr/hr. Bottles of product solution reading in excess of 300 mr/hr, maximum allowable for shipment. were reprocessed in the second-cycle solvent extraction system (Thorex) and reconcentrated. The products from seven runs had radiation levels in excess of 300 mr/hr at the time of concentration, or the activities had grown to that level by the time of shipment. The …

The heat transfer and fluid friction characteristics have been determined for a liquid flowing parallel to the tube bundle of a heat exchanger consisting of one hundred and two 1/16-inch O.D. tubes arranged in a delta or triangular array. These results may be expressed by empirical equations.