Geologic and radiometric investigations of the CuzcoAyaviri region in southern Peru were made in a search for geologic features or structures which might be favorable for the occurrence of uranium. Outcrops consist of Lower Paleozoic sedimentary and metamorphic rocks; Permian to Carboniferous volcanic flows, tuffs, breccia and agglomerate, together with sedimentary rocks; and Cretaceous and sedimentary rocks. Cretaceous to Tertiary igneous rocks are acidic intrusives and extrusive rhyolite, dacite and trachyte. Tertiary to Quaternary volcanic tuffs, breccias and agglomerates are also present. Although no anomalous radioactivity was observed, favorable geologic features for the occurrence of uranium were noted at two localities. (auth)

Since the issuance of the Purex Phase II flowsheet a number of improvements have been suggested and additional information has been obtained. The purpose of this document is to summarize the more recent information and to bring the two-cycle chemical flowsheet up to date. Later changes will be similarly documented. The Phase II terminology has been dropped as the primary objective of the two-cycle conversion is economy rather than capacity. As mentioned in reference (1), the flowsheet has been designed to best use existing equipment and does not necessarily represent the optimum flowsheet for new plant construction.

The masses of the isotopes of the heaviest elements have been calculated from known decay data in the region, extended by means of decay energies calculated from closed decay-energy cycles and estimated from the systematics of alpha and beta decay energies. The absolute values of the masses are based on the mass-spectrometrically determined mass of Pb{sup 208} and a few measured neutron binding energies. The half-life systematics of alpha decay and spontaneous fission are also presented, and some predictions of the properties of as yet undiscovered nuclides are made.

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The over-all design of the Argonne Low Power Reactor is presented. Detailed design data are given as well as information concerning the hydrology, seismology, and meteorology of the building site (NRTS). In addition, a description of the reactor instrumentation and control, mechanical design, heat transfer, and related physics are presented. A full description of the power plant, including the steam and electrical systems, is also given, as well as the operating procedure for both normal and emergency conditions. Over-all reac tor safety is evaluated. Diagrams and graphs are included. (J.R.D.)

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The references of this resume have been obtained largely from a card index compiled at Argonne National Lab. The source of information has been arranged in chronological order according to subject matter, then document number. (auth)

Reference designs for pressurized and direct-boiling D/sub 2/O reactors were prepared for electrical outputs of 20, 100, and 250 electrical Mw. A number of possible core designs were considered and those utilized which seemed most appropriate to give low-cost power. The technology and costs available today were employed in the preparation of the over-all plant designs. The Consolidated Western Steel Division of U. S. Steel Corporation assisted by preparing a comprehensive report on the design of large pressure vessels and containment vessels. Zr-clad U fuel elements were used as the study basis, but the effect of using UO/sub 2/ and stainless steel cladding was also considered. The principal results found were: (1) Over a wide range of operating conditions snd economic situations, enriched U (up to perhaps 1.4% U/sup 235/) is presently more economic to employ in D/sub 2/O reactors than is natural U. (2) In the longer range, the use of natural U may become more economic as Zr fabrication costs decrease, continuous charge-discharge devices are developed to permit longer exposure levels, and pressure-vessel technology advances so that the large critical masses and core diameters required are not such sn economic penalty on the natural U. The results agree …

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Presented at organizational meeting of the Southwestern Section, Assoc. for Computing Machinery, Oct. A geometric progression modulo n is defined, and methods are given for predicting its period. Its usefulness as a random number generator is discussed. (auth)

Plutonium hexafluoride is decomposed by heat, by its alpha radiation, and by reactions with most materials of construction. Laboratory experiments were performed to investigate means by which plutonium losses due to these reactions can be minimized during vapor-phase transfers of the compound. The experiments showed that plutonium hexafluoride vapor could be transferred satisfactorily through well fluorinated nickel equipment in a stream of fluorine or helium. The decomposition product of plutonium hexafluoride was refluorinated at 250 deg C by fluorine. (auth)

The U/sup 235/ fission spectrum is tabulated as a function of energy for two analytic representations. The table contains the distribution functions, their first derivatives, and their first integrals up to 10 Mev. (auth)

A parametric study of the potential and performance of natural circulation boiling nuclear reactors is presented. Analyses are based on engineering data and correlation extrapolations obtained from boiling studies at Argonne. Graphs are used extensively to show interrelationships of power density, system pressure, average core coolant density, core height, riser height, channel hydraulic diameter, recirculation flow rate, and exit steam volume fraction. Interesting aspects of reactor design and their diameter, recirculation flow rate, and exit steam volume fraction. Interesting aspects of reactor design and their effects on performance are discussed briefly. (auth)

Spert--I-- A brief resume of A'' core experiments is presented and the results of some of the static measurements with the B'' core are shown. It was found that four usable cores are possible with the removable-plate B'' fuel assemblies. The measurements made to date have been with a 24 fuel plate/ assembly, 32 assembly core, and include rod worth, flux distribution, temperature coefficient and preliminary void coefficient studies. Spert--II-- The construction contract was let amd construction started in August. Spert--III -- The control system circuit drawings are essentially complete. Data Reduction and Interpretation-- The progress made in reducing the large raw data backlog from the Spert I A'' core experiments is shown. Work is continuing on the calculation of reactivity behavior during a transient, with the principal area of investigation being that of a boiling or slightiy subcooled experiments. The use of other calculational procedures as a check on the reactivity behavior work is being investigated. Theoretical-- The critical masses for the various possible B'' cores were calculated, and agree quite well with the experimentally determined values. Some machine calculations of the temperature and void effect with the 32 assembly core were made, but no direct comparison with empirical …

A unique concept is featured in the adaptation of a Bausch and Lomb Research Metallograph for remote metallography at Argonne National Laboratory. The metallograph is placed outside and adjacent to the metallographic preparation hot cell, and only the microscope section is shielded. This arrangement results in the decisive advantages of simplified adaptation for remote operation, and unaltered optical system, and greatly reduced shielding bulk. A mechanical transfer system shuttles the irradiated specimens between cave and metallograph. All controls and adjustments of the metallograph are available for use in remote metallography; microscope adjustments are manipulated with simple, hand-operated mechanical linkages; stage adjustments are motorized; camera and light source, outside the shield, are operated by hand in the normal manner. The shield, 1 1/4 in. of depleted U incorporated in the stage plus 4 in. of Pb surrounding both microscope and stage, provides for continuous operation with the equivalent of up to 50 c of Co activity. Lead-glass windows permit viewing; a reversible turret and door in the shield cubicle permit easy access to the microscope and stage. (auth)

The feasibility of constrncting a digital computer about one hundrnd times faster than present computers, such as ILLIAC, using transistonized circuits and other presently avnilable components and techniques is reported. The results of two design studies are discussed. One involves a minimum of buffer storage in the form of transistor registers, and the other involves a moderrts ammount of buffer storage in the form of a small-capacity, high-speed, random-access buffer memory. Tbe former design is emphasized because its equipment requiremente can be presentiy met. Two controls are used, arithmetic control and advanced control, as well as buffer storage for instructions and operands, and by such meaan various units of the computer are kept in simultaneous operation. The relative speed of the proposed computer compared to that of existing machines depends upon the problem. For problemas dominated by arithmetic operations, it is estimated that the proposed computer will be 100 to 200 times faster than computers such as ILLLAC. For problem dominated by logical and combinatorial operations, the gain in speed will be at least 50times. The computer has a random-access word-arraagement memory of 8192 words of 52 units each with an access time of 1.5 mu sec. The arithmetic unit …

Presented at the Eighth Meeting of the Supersonic Wind-Tunnel Assoc., Seattle, Wash. Oct. 1957. The Dampometer represents a harmonically damped oscillation by a rotating vector in such a way that the length of the vector is proportional to the damping. The device was designed for use with a forced oscillation dynamic testing, and its modification for use with a free oscillation rig is described. (T.R.H.)

Apparatus was developed for vapor depositing molybdenum on the outside of O.1835-in.-OD by 20-in.-long Type 304 stainless steel tubing by hydrogen reduction of molybdenum pentachloride or by thermal decomposition of molybdenum hexacarbonyl, both processes being carried out at reduced pressure. The coatings obtained were uniform, but quite brittle. Apparatus also was developed for vapor depositing niobium on the inside of the abovementioned tubing by hydrogen reduction of niobium pentachloride at reduced pressure. These coatings were uniform, adherent, nonperous, and moderately ductile. (auth)

Presented at the Eight Meeting of the Supersonic Wind- Tunnel Association, Seattle, Wash., Oct. 1957. The two control systems are compared for nominal stagnation pressures of 16 and 34 psia. The improved performance of system B has resulted in increased Mach number capability of the tunnel, improved Mach number control during a run, and an increase in the run frequency. (W.L.H.)

>Abstracts of published reports and a list of the internal memos of general interest are included. The radial vari:dtion of magnetic field as a function of thc magnitude of the central field was measured and investigated with model magnets. Measurements on end-effects were made on the 1/7-scale model magnet. The calculated and measured fields at the ramp and are shown for a low field value where there is no saturation and such calculations are expected to be valid. The variation in the effective magnetic end position as function of the central field value and also thc radial shape of the cffective end as a function of central field value are shown. Flow measurements were made for the various sizes of Cu tubing that could be used for model magnet coils. A block diagram of could new generator regulator for the G. E. generator is given. A schematic diagram of the pulse circuit for the 1/4-scale model magnet and an idealized voltage waveform on an inductivc load are shown. A plan view of the ring magnet is given showing the basic dimensions and a proposed arrangement of the various basic components which will occupy the straight sections. A plan view of …

ZPR-V is a zero-power, coupled fast-thermal critical assembly involving a dilute fast core and a H/sub 2/O-moderated, enriched U thermal annulus. The two regions are coupled through a natural U isolation blanket. This facility is useful in studying some of the properties of dilute fast reactor systems as well as those of coupled fast-thermal power breeders. Recent emphasis has been on the latter aspect of the problem and an investigation of the coupled aspects of the system has been made. An important parameter in the coupling concept is the division of reactivity. This can be determined by means of fast fuel substitutions and 1/v poisoning of the thermal annulus in conjunction with theoretical calculations. Auxiliary information obtained in such a procedure is the fast fuel worth throughout the core and the prompt neutron lifetime of the whole system. A second important pnrameter, S/sub 1/S/sub 2/, is the relative number of neutrons emitted per unit time due to fast and slow fissions. Information regarding this quantity can be obtained with the aid of U/sup 235/ and U/sup 238/ fission distributions. Measurenments of thc above parameters were made for the case of a U/sup 238/:U/sup 235/ atomic ratio of 5:1 in the …

The uranium--niobium binary system exhibits a continuous series of solid solutions above 850 deg C. At lower temperatures a miscibility gap exists, containing a niobium-rich and a uranium-rich body-centered cubic phase. A monotectoid transformation occurs at 634 deg C. The beta-uranium phase is restricted by niobium and disappears at 4 wt.% Nb. Below 634 deg C alpha uranium and the niobium-rich gamma co-exist. The uranium--niobium--zirconium ternary system exhibits a continuous series of solid solutions at high temperatures. Miscibility gaps in the uranium-niobium and uranium--zirconium binary systems close with addition of the third element. Addition of both zirconium and niobium stabilizes the body-centered cubic gamma phase to lower temperatures. The beta-uranium phase is eliminated in ternary alloys of 4 wt.% Nb or more. The delta phase of the uranium-zirconium binary system extends into the ternary system to no more than 10 wt.% Nb. Over the major portion of the uranium-rich corner of the ternary system the equilibrium phases are alpha-U and gamma solid solution. The uranium-niobium binary system is the more dominant of the limiting systems. No new ternary phases were found. The relation of microstructures to irradiation stability is discussed. The relation of lattice strain to limits of solid solubility …

Thirty-seven sterile materials of common construction usage, common lubricants, and samples of wearing apparel were injected as finely divided particles into the subcutaneous soft tissues of guinea pigs, each in six different sites. At intervals of 3, 7, 14, 21, 30, 65, or 90 days, an inoculation site of each material was excised, in toto, fixed, and examined microscopically. In addition, ten selected materials were injected into the liver and spleen and deposited on the omentum and mesentery of four guinea pigs for each material type. At intervals of 7, 14, 21, and 30 days, one of each group of four animals was sacrificed and a block of tissue containing the inoculum was removed from the tissues and organs, fixed, and examined histologically. The majority of materials induced only a mild and delayed inflammatory response followed by encapsulation at the end of 14 days and a relatively inert fibrous nodule produced by the 2lst or 30th day. Copper particles incited a marked inflammatory response with abscess formation which persisted until the 90th day, although showing signs of subsiding at this time. Cudmium lesions were characterized by a peculiar zone of necrosis about the particle aggregate which persisted until the 60th …