The Pinot Project was designed to provide some indication of the extent to which gases from a confined underground explosion in oil shale would migrate parallel to the bedding planes. At 0800 on Aug. 2, 1960, 946 lb of nitromethane was fired in shot hole No. 1. There was no visible damage to the mine adit or to any structure associated with cation of the extent to which gases from a confined underground explosion in oil shale would migrate parallel to the bedding planes. At 0800 on Aug. 2, 1960, 946 lb of nitromethane was fired in shot hole No. 1. There was no visible damage to the mine adit or to any stnucture associated with the workings. Gas samples collected from sampling holes near the shot hole were analyzed for Kr/sup 85/, which had been included with the nitromethane as a tracer. It appeared that the Kr/sup 85/ concentration in the samples out to 50 ft was more or less independent of space and time between +2 and +50 hr. Relativsly little Kr/sup 85/ was detected at 125 ft and none beyond. About (20 plus or minus 10)% of the Kr/sup 85/ escaped into ths adit. The results of …

Foreword: This report covering the technical feasibility and economic potential of the VMR completes the requirements of Phases II and III of the program outlined in American-Standard Proposal No. P-470A.

>A study was made of the energy levels of Pu/sup 238/ which are populated by Np/sup 238/ beta decay, by an examination of the Np/sup 238/ conversion electron spectrum in high-resolution beta spectrographs. The general features of the level scheme as previously given were unchanged but several new transitions were observed, with energies of 119.8, 871, 943, 989, and 1034 kev. Two new levels are postulated at 915 and 1034 kev which accommodate all but the 943-kev transition. A possible assignment of the 943-kev transition to the (0+.0) state of the beta vibrational band is discussed. In addition, the weak 885-kev transition from the 2+ state of the gamma -vibrational band to the 4+ state of the ground band was seen and its relative intensity determined. Comparisons were made of the experimental relative transition intensities of the three photons depopulating this band with those predicted from the rules of Alaga et al.; only fair agreement was noted. A discussion is given of the beta decay branchings and log ft values of Np/sup 238/ decay in terms of the postulated characters of the Pu/sup 238/ states and the measured spin of Np/sup 238/. (auth)

None

Annual summary documenting research related to metallurgy at Ames Laboratory. Discussions are given of developments in the following areas: the preparation and purification of metals; phase equlibria and thermodynamic properties of alloys; physical and mechanical properties of metals and alloys; solid state studies; separation processes; and investigations dealing with diffusion, oxidation, and reduction, halide reactions, preparations, vapor pressure measurements, and transport reactions. (B.O.G.)

The demands of the scientific programs of the Lawrence Radiation Laboratory at the Nevada Test Site have necessitated the development of special drill hole survey techniques. These techniques, in general, have made possible the attainment of greater survey accuracies than are ordinarily obtained by the drilling industry in the course of normal survey work. For drill holes requiring a moderately high degree of location accuracy, standard survey equipment, manufactured by Eastman Oil Well Survey Company was adapted by LRL to meet this need. Where an extremely high degree of survey accuracy and control of drilling effort is necessary, such as in the drilling and survey of line-of-sight holes, special optical equipment was developed. The modifications of equipment, refinements in procedures, and special techniques necessary to adapt this equipment to meet the more demanding accuracy requirements of scientific programs are discussed. The overall techniques of survey, equipment used, and the accuracies obtained together with results of completed surveys showing a comparison with standard land survey methods are also discussed and illustrated in some detail.

Report issued by the Argonne National Laboratory over studies conducted on designs for a lunar power plant. As stated in the abstract, "a concept of a nuclear power plant to be assembled on earth and operated on the moon in presented" (p. 9). This report includes tables, illustrations, and photographs.

A concept of a nuclear power plant to be assembled on earth and operated on the moon is presented. The two principal design objectives are reliability and high specific power. Wherever there is an incompatibility between these two objectives, the decision favors reliability. The design is based on the premise that the power plant must be designed on the basis of current technology and with a minimum amount of research and development. The principal components consist of a fast reactor in a direct cycle with a mercury-vapor turbine. The high- frequency generator, hydrogen compressor for the generator cooling system, mercury-recirculating pump, and condensate pump are on an extension of the turbine shaft. Ths mercury vapor is condensed and the hydrogen cooled in wing radiators. The reactor is of a construction quite similar to EBR-I Mark IlI for which there is a large amount of operating experience. The radiator is a vertical tube-and-fin type built in concentric cylindrical sections of increseing diameter. The curved headers are connected by swivel joints so that, upon arrival, the radiator can be quickly unfolded from the compact cylindrical package it formed during transportation. (auth)

This paper is concerned with the spectral theory of closed operators in Hilbert space determined by the Laplace operator and certain general boundary conditions. Using the method of J.W. Calkin, we treat the case of a bounded domain in E(m) with C(1,1) boundary, and, in addition, extend the method to cover the case for which the operator L in the boundary condition is not necessarily self-adjoint. It is shown that there exists an appropriate linear close of functions [formula] such that the operator in the Hilbert space [formula] and [formula] is self-adjoint. In potential theoretic terms it is the set of all sums p + h, where p is the potential due to a charge g in G and h is the potential due to a surface charge f on ∂G and h is a potential due to a surface charge f on G, where g and f are, respectively, square integrable over G and ∂G

The thermal-neutron flux prevailing near the upper hole in the HRE-2 core wall was determined from measurements of the induced activity in a specimen cut from the edge of the hole. The specimen was removed following run 21 and was thus exposed to reactor neutrons during runs 13, 14, 16,17, 18. 19, 20, and 21. The neutron flux, calculated for an average core power level of 2 Mw, was 2.8 x10^13 neutrons/cm^2 sec. the core wall area from which the specimen was removed was located approximately 16-in. from the core center.

Complete series of yttrium-titanium and yttrium-zirconium alloys was tested in tension at room temperature. Ultimate tensile strength, yield strength, and reduction in area data are reported for the alloys. Yield point phenomena were encountered in both alloy systems. (auth)

A technical and economic evaluation of a mercury-cooled fast breeder reactor is presented. The objectives of the program were to establish the technical feasibility of a fast breeder reactor cooled with boiling mercury and to evaluate the long-range potential of such a reactor power plant for production of economic power. Details of the conceptual design of a 100-Mw(e) reactor and system are discussed. The power cost from a mercury cooled fast breeder reactor was estimated as 21.4 mills/kwh which is competitive with the power cost for the initial Enrico Fermi plant. It was concluded that this reactor concept is technically feasible and has promising long-range economic potential. (M.C.G.)

One hundred and seventy five grams of americium in a hydrochloric acid solution varying from 1 to 7 N was converted to americium dioxide. Americium oxalate was precipitated from 0.1 N HCI with 100% excess oxalic acid and was converted to the dioxide by calcination at 800 ts C in air. The solubility losses in the oxalate precipitation filtrate averaged approximately 7 mg/liter of solution, with a total loss of 0.09%. (auth)

Abstract: This report presents the vapor pressures versus temperature data graphically for the rare earth elements, yttrium and scandium.

Fuel element corrosion studies designed to and in selecting and evaluating SM-2 fuel element welding techniques are discussed. Tests on type 347 ss plate type fuel elements welded by the selected tungsten inert gas technique showed good corrosion integrity of specimens under a variety of conditions including a 500-hr test under simulated SM-2 conditions of flow and coolant chemistry. (auth)

The effect of two neutron poisons, baron and cadmium, on the rate of dissolution of high-density 95% ThO/sub 2/-5% UO/sub 2/ pellets in the Zirflex Process was determined. Dissolution of U-10% Mo alloy in boiling HNO/sub 3/ resulted in a precipitation of uranyl molybdates. Air caused greater uranium and thorium losses during decladding of ThO/sub 2/-UO/sub 2/ fuel than irradiation. Processing of U-Mo fuel by a Zircex type process is discussed. Two leaches of graphitized fuel with 90% HNO/sub 3/ recovered more than 99% of the uranium. Irradiation of synthetic ThO/sub 2/-UO/sub 2/ fuel solution to 5 and 10 watt-hr/l in a Co/sup 60/ source resulted in about a 50% decrease in decontamination factor using the acid-Thorex flowsheet. Corrosion of titanium, tantalum, and Ni-o-nel in Thorex solution and titanium corrosion in various molybdenum core alloy solutions were investigated. The solubilities of ferric mono- and dibutyl phosphates in HNO/sub 3/ and 30% TBP-Amsco-HNO/sub 3/ solutions were determined. Fission product concentrations expected in Purex waste from processing Yankee Atomic Reactor fuel were calculated. Chemical applications of nuclear explosions to H/sup 3/ exchange, reduction of CaSO/sub 4/, and Gnome sampling are discussed. (For preceding period see CF-60-6-108.) (M.C.G.)

The exposures calculated from these plans are designed to maximize plant return on the basis that the only restraint on metal usage is that imposed by the economics of the plutonium production process and associated uranium cycle. When metal throughput in limited by ex-reactor physical capabilities to a level lower than the unrestrained requirements, exposures higher than those recommended in this document would be indicated. In essence then, these plans represent minimum economical exposures for current production fuel types, on the basis of attempting to maximize plant returns. The adjustments recommended herein, stem solely from revised estimates of the metal performance level indicies (C{sub R} values) of the various metal types.

Although a fuel reactor job procedure has not yet been prepared, techniques and equipment used in a current production test are adequate with minor modifications for full reactor Parker fitting reaming. With existing reactor hardware, available flow increases at B, D, and F Reactors would be limited to about 2,500 gpm. The extent of additional rear face piping problems which may be encountered as a result of reaming cannot in several instances be predicted with confidence at this time. It is expected that preliminary answers to currently foreseen problems will be available by April 1, 1961. To some extent, however, this is dependent on production tests under way or proposed, and will require coordination with various Manufacturing Operations. For vibration and flow problems in the downcomer approach piping, conclusive answers may not be available before July, 196l, although there is no positive evidence that the flow increases cannot be absorbed. Increased pressurization of effluent line junction boxes at 105-D has been solved by improved box venting. Increased flows resulting from reaming may require still greater venting capacity, which would be available for capital expenditures on the order of $3,000--$5,000 per area.

A chemical flowsheet is proposed for recovery of strontium and rare earths from Purex wastes. The iron in the waste is first complexed with tartrate and the pH is adjusted with caustic. Strontium and rare earths are extracted by a solvent comprised of di(2-ethylhexyl)phosphoric--sodium di (2-ethylhexyl) phosphate--tributyl phosphate -- Amsco 125-82. and are stripped with nitric acid. Processing the strip product through additional solvent extraction cycles yields isolated, concentrated strontium and rare earth fractions.

In the Communications of the ACM of April, 1960, p. 240, there appeared two Algol algorithms for the computation of In, the modified Bessel function of the first kind. One of these algorithms uses a convergent series and the other an asymptotic series. Their author, Dorothea S. Clarke, did not give any information with regard to which algorithm is more appropriate in a given situation (a given situation meaning the computation of In (x) for a definite pair of numbers n and x). Such information is necessary, however, if the algorithms are to be useful, particularly since the asymptotic series is in many cases not valid.

This is the second quarterly report that documents a system of mass flow that can record measurements of homogeneous flow, slurries, highly corrosive fluids and multiphase fluids, additionally considering pressure drops, measuring external to the flow, ruggedness and reliability.

Activities in a development program for a mass flow system capable of measuring homogeneous flow, slurries, highly corrosive fluids, and multiphase fluids are reported. The first experimental mass flow meter is nearly complete, and the required intensity of the radioactive source for mass measurements is being determined. Design of the vibrating reeds for the sources are completed. Absorption measurements at energies <100 kev indicate that composition effects are present, however, the effect is not considered serious since the system can be calibrated for each particular material. (J.R.D.)

Technical report. From Abstract : "The absorption and elution of the anionic nitrate complex of neptunium (IV) were studied with several anion exchange resins and under a wide variety of conditions." From Introduction : "The objective of this study was to provide a technical basis for selecting process conditions for the recovery of Np."

Abstract: In August 1958 two geologists of the Instituto de Investigaciones Geológicas de Chile made a one-week reconnaissance for uranium of the Arica area in northern Chile.