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The basis for design of mixer-settlers for the Amex solvent extraction process, which uses long-chain amines dissolved in a hydrocarbon diluent for the recovery of U from acid sulfate solutions typical of those obtained in U ore processing, was determined by a unit-operations study in scale-model units. Long- term recycle tests in countercurrent equipment demonstrated the stability of amines and the general feasibility of the Amex process. Mass transfer rates of U for both extraction and stripping are large, and greater than 90% stage efficiency was readily obtained. The flow capacity of gravity settlers is generally limited by a dispersion band, which increases exponentially with flow rate. The scaleup of settlers is based on the constant flow rate of dispersed phase per unit settler area and constant band thickness. The nominal flow capacity (50% of flooding) ranged from 0.4 to 0.8 gpm/ft/sup 2/, depending on the type of dispersion and amine used. The capacity can be increased (fourfold) by using packing wetted by the dispersed phase. Emulsion stabilized by silica (the worst offender) can be minimized by controlling the mixing in order to form solvent-continuous dispersions, which also minimizes entrainment of solvent in the aqueous waste. (auth)

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The spectrum of neutrons scattered from Ta/sup 181/ was please delete the above abstract--------

Optimization of the reactor process involves the knowledge of the longitudinal flux distribution on a semicontinuous, routine basis. The nonpoisonous spline was proposed as a way for obtaining flux traverses at any time during reactor operation, in virtually any location in the core. This report summarizes the findings of a feasibility study conducted in conjunction with PITA-18 and thus serves as a termination of the test phase of spline traversing.

Three Fortran programs, written for the IBM-704 computer, process the data from multichannel pulse-height analyzers in order to derive the Q values and differential cross sections of the groups observed. The standard deviations of the derived Q values and of the differential cross sections are also computed. With another program that was written, the effects of impurities can be subtracted from pulse-height spectra observed when a target contains a mixture of nuclides. A fifth program computes the centerof-mass transformation quantities by means of the exact relativistic equations. (auth)

Abstract: Three irradiation experiments are described which have been designed to study the behavior of fuel elements in a reactors superheated steam environment. The experiments were conducted in the Superheat Advanced Demonstration Experiment loop, Vallecitos Boiling Water Reactor. The results obtained demonstrated that 304 stainless steel fuel clad in unsatisfactory for use in nuclear super heat fuel sheath designs where plastic strain or plastic deformation is allowed to occur. The results were in agreement with those reported for a previous experiment in SADE (SH-4B) and constituted the basis for change in direction of the superheat fuel program in regard to both design and fuel sheath selection.

Report reviewing literature that concerns "the compatibility of stainless steels and nickel-base alloys with various gases which might be present in or around a high temperature nuclear reactor" (p. 2).

Report summarizing "the utilization of the Health Physics Research reactor and a Co60 source during Operation BREN" and offers related meteorological data relating radiation emissions.

Abstract: The physical property variation of superheated steam differs sufficiently from most other gases to warrant experimental investigation of heat transfer performance. Results are reported here of measurements made in a uniformly heated circular duct with steam at 1000 psi. The data agree very well with the expression use for design purposes, which is based on information in the literature for heating of other gases as well as steam. This work was a continuation of that performed under Task (Heat Transfer) of the Nuclear Superheat Project, AEC Contract AT(04-3)-189, Project Agreement 13.

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A system analysis was performed to establish the design and performance characteristics of 250- and 1000-Mev MHD generators. The results are presented, and the necessary equations are derived. The results of environmental tests that investigated boundary and bulk conductivity, structural concepts, and combustion phenomena are included. The other five volumes of the report are summarized, together with the principal conclusions. (D.C.W.)

The chemical behavior of iodine-131 in stack air from this site's Purex process is reported. The radioiodine in the stack gases apparently consists of variable proportions of molecular vapor and other forms of iodine, thus causing the efficiencies for most collection media to vary widely. Activated charcoal is a satisfactory collection medium although Process gases (ammonia and oxides of nitrogen) lower the efficiency of the charcoal from 99 to 88%. Ambient temperature and humidity had no effect on deposition and retention of iodine in long stainless steel sampling lines. Process conditions did have an effect and estimates of iodine released were 10 to 15% low due to this line loss. (auth)

In uranium with alloying additions of up to 400 ppm Fe and up to 800 ppm of either Si or Al, the various U-containing phases were examined with the electron microscope. These phases were also extracted chemically and identified by electron diffraction. During gamma -phase heat treatments, the alloying additions, as well as impurity atoms, segregate into networks of incipient'' precipitates that can be seen only afier certain etching treatments. (auth)

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A general review is presented of space propulsion projects with respect to materials requirements. The characteristics and requirements of Pluto (nuclear ramjet) are described. The general requirements for propulsion in space and the classes of nuclear rockets are outlined. Materials requirements and problems are discussed in detail for the heat transfer nuclear rocket (Rover). (D.L.C.)

The physics calculations to be performed on the Consumers On-Line Process Computer are reported. As a result of these calculations, a three-dimensional power shape is simulated, a reactivity balance is approximated, and the neutron exposure of each third of fuel bundle and control rod are accumulated. The work was reported as a part of the Consumers Research and Development Program.

This report describes the final design of the Fuel Element Rupture Testing Facility and summarizes the safeguards analyses of the design and plans for operation.

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"The study of the toxicity of Ra and MsTh(Ra/sup 228/) in humans was continued. Several Thorotrast cases were also examined. Physical and clinical studies were made on 151 persons. In all cases possible gamma ray measurements were made of Ra and MsTh decay products retained in the body, alpha -ray measurements of Rn and Rn/sup 220/ in breath, a complete medical history was taken, a complete x-ray examination was made of the skeleton, and urinalysis, hematological, and blood chemistry studies were made."

Separate abstracts were prepared for 7 sections of this report. A list is included of publications during the period covered by this report. (C.H.)

Separate abstracts were prepared for thirty-three of a total of thirty- four sections in the report. The section for which no abstract was prepared concerned construction and out-of-pile testing of a third in-pile slurry loop experiment. (J.R.D.)

This monthly technical report details activities in reactor physics research and development during the month of April 1963.

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