Description of a data collection and reporting system which was devised and installed in the Union Carbide Nuclear Company's Y-12 Plant Maintenance Division.

A new theory is proposed to evaluate individual mass-transfer coefficients without actual experiment.

This report summarizes several reports pertaining to uranium processing.

Abstract: "Measurements have been made of the cross sections for the reactions Id-6(n, dn)He-4 and Li-7(n, tn)He-4 over an incident neutron energy range of 5 - 14 MeV. The energy and angular distributions of all reaction products were determined."

Abstract: Ground-water test well 2 was drilled to a depth of 3,422 feet with rotary and cable tool drilling equipment.

This technical report describes a pulse height converter that employs the R.F. vernier method. This particular converter has been developed for use with the pulsed beam facility of the BNL Van de Graaff. This report then details a number of tests of the converter made using a RIDL model 34-12, 400-channel analyzer. The report includes 6 figures and 4 circuit diagrams to accompany the findings.

This technical report details and outlines the BGRR facility's operations and performance record over a period of twelve years. The author of this report finds that the reactor is "one of the most stable and dependable in the business." The report includes two figures.

Technical report outlining an experiment to introduce radiation to maize plants after pollination to produce blue-florescent and albino seedlings.

This report describes procedures to "secure acceptable samples of bile from unanesthetized, nondepleted rats and sequential quantitative analysis with negligible experimental failure"--from abstract.

This report studies the thermal decomposition of unirradiated and heavily reactor irradiated colloidal [alpha] - PbH6.

This report reviews the published work on the thermochemistry of the liquid alloys of bismuth with Th, Pa, U, and Pu and the high-yield fission products, and presents in a unified form the authors' own results in this field.

This report describes a system that uses positron emitting isotopes for locating brain tumors.

This report measures the cross sections of isotopes for 14.5 MeV neutrons and compares the author's results with calculated and existing literature values.

This report seeks to "develop a practical method of evaluating the eddy diffusivity of heat transfer for liquid metals, so that it can be incorporated into the more or less standard theoretical methods to give heat transfer coefficients which are in reasonable agreement with experimental facts"--from introduction.

This report details a study of the vapor pressures of deuteroethylenes and C13 ethylene.

This report discusses some of the problems in the calculation of isotope effects on the vibrational frequencies of the condensed phase.

Introduction: Sargent & Lundy was authorized on November 1, 1960, to make an economic and technical feasibility study of various reactor containment designs which are being utilized for several power plants now under construction.

Convair-Fort Worth, under contract to the U.S. Army Engineer Research and Development Laboratories, performed experiments to obtain data for use in applying field materials to shield portable nuclear-reactor power plants.

"An investigation was made into the various processes for the fixation of mixed fission products as solids in order to determine the extent they could be utilized as heat sources for thermoelectric generators. Generators of up to ten watts can be designed and built with state-of-art'' thermoelectric materials and mixed fission products soon to be available from the ldaho Falls calcination pilot plant. Mixed fission products from other processes and plants to be on stream'' in this decade will be capable of fueling practical generators into the kilowatt range using thermoelectric materials available in the same time period. A survey was made on current research and development efforts on waste fixation processes. Studies showed that a wide range of power densities (from 0.002 to 0.2 watts per cubic centimeter) will be available from calcined fission product wasted. An experimental program for the consolidation of low density, Idaho Chemical Processing Plant alumina type wastes is reviewed. Preliminary results indicated that densification factors of three to four are readily obtainable for such wastes."

"The performance of the Model I electrostatic precipitator sampler in recent field and laboratory tests is described and discussed. Two of the four precipitator-bearing balloon flights during this interval reached the floating altitude of approximates 105,000 feet, and the precipitator operated efficiently on both. One sample was collected at the nominal design flowrate of approximates 100 cfm, and the second at approximates -200 cfm. Comparison of the deposition profiles of the stratospheric samples with those obtained under controlled conditions in the altitude chamber indicates that the field samples were collected with >90% efficiency. The laboratory tests also showed that the performance capability of the precipitator improves with increasing precipitator current, and with increasing altitude. One of the above balloon flights carried two Model A-I altimeters with recorder outputs. The two records were identical within plus or minus 250 feet. In addition, variations in altitude indications were consistent with the less sensitive aneroid barocoder measurements from the same flight. A revised Model A-I altimeter with a telemeterable output signal has been designed and constructed. The frequency of the signal is a function of the altitude. A preliminary design concept for a flowmeter with negligible flow resistance is described. It would utilize …

At the present time, cerium-144 and premtheium-147 are the two fission product rare earths that appear most promising for use as the heat source in isotopic power units. Under proper conditions, cerium and the trivalent rare earths can be extracted from the Purex fission product waste stream as an insoluble sodium-rare earth double sulfate. A reprecipitation as the double sulfate, dissolution of the hydroxide, serves to give almost complete separation from the corrosion products, inert constituents of the waste, and from most of the fission products. The cerium and the trivalent rare earths must then be separated from each other. In the case of cerium recovery, it is necessary to remove the trivalent rare earths in order to maximize the specific activity of the cerium. If promethium is the desired product, a preliminary cerium separation is desirable to protect the ion-exchange resin (used for separating promethium from its adjacent rare earths) from the intense high-energy radiation from cerium.

Technical report. From Summary : "At the present time arsenazo appears to be widely used for the spectrophotometric determination of rare earths. Unfortunately, the method is not selective. The separation of rare earths and yttrium from interfering elements has been studied, and the following method has been proposed. Rare earths are precipitated as fluorides using fluorides using calcium fluoride as the carrier. Thorium and zirconium are removed by extraction with thenoyltrifluoroacetone (TTA) in xylene at pH 1.3. Small amounts of residual aluminum, iron, etc. are removed by extraction with 8-quinolinolchloroform at pH 4.5. Rare earths are separated from calcium by TTA extraction at the same pH, and they are then back-extracted into 1 M nitric acid. After evaporation of the solution, the rare earths are determined spectrophotometrically with arsenazo."

From introduction: "In this paper, data obtained by Hunter and by the author are reported from laboratory investigations of (1) surge flow introduced into empty simply drains, (2) attenuation of surges in simple drains, (3) continuous full-section flow in simple drains under substantially steady, uniform conditions, (4) steady flow in compound drains, and (5) surge flow introduced through a branch drain into the side or top of a main drain carrying steady flow."

From Present Programs: "There has been a gradual expansion of the Sr^90 food analysis program to include vegetable foods and finally entire diets. In some cases the analyses have also been extended to other nuclides but these data are so limited that they will not be emphasized in this report. It is expected that considerable data on Ra^226 and other naturally occurring radionuclides will be generated in coming year."