The nonspherically symmetric solutions to the Bardeen-Cooper-Schrieffer theory are given a physical interpretation in terms of an anisotropic fluid model. These solutions have been used previously to predict a phase transition in liquid by He{sup 3} by Emery and Sessler and Anderson, Morel, Brueckner, and Soda. An investigation of the flow properties of such systems is made that involves the calculation of the effective mass for flow in a straight channel and the moment of inertia of a cylindrical container of the liquid. The angular dependent energy-gap characteristic of this type of theory leads to an effective mass for flow that depends on the angle between the axis of symmetry of the fluid and the direction of flow. It also vanishes as the absolute temperature tends to zero, although not as rapidly as for a spherically symmetric gap. The moment of inertia, when the symmetry direction for the fluid and the rotation axis are the same, is simply related to the mass for flow.

The recoil-proton polarization in {pi}{sup +}-p elastic scattering at 310-Mev incident-pion laboratory kinetic energy has been experimentally measured at four scattering angles with scintillation counters. Polarization values obtained, related rms experimental errors, and mean center-of-mass recoil angles are: +0.044 {+-} 0.062 at 114.2 deg. =0.164 {+-} 0.057 at 124.5 deg, -0.155 {+-} 0.044 at 133.8 deg, and -0.162 {+-} 0.037 at 145.2 deg. The sign of the polarization is defined to be positive when a preponderance of the recoil protons had their spin vectors pointing in the direction of {rvec P}{sub i} x {rvec p}{sub f}, where this quantity is the cross product of the initial and final momentum vectors of the conjugate pions. A beam of 1 x 10{sup 6} pions per sec incident upon a 1.0-g/cm{sup 2}-thick liquid-hydrogen target produced the recoil protons, which were then scattered by a carbon target at a mean energy varying with recoil angle from 113 to 141 Mev. The polarization of the recoil protons was analyzed by measuring the asymmetry produced in the carbon scattering. A proton beam of known polarization was used to determine the analyzing ability (measured asymmetry divided by the polarization of the incident protons) of the system at …

A comprehensive phase-shift analysis of {pi}{sup +}-p elastic-scattering data at 310-Mev incident-pion laboratory kinetic energy has been performed. The experimental data utilized include measurements of the differential and total cross sections and of the recoil-proton polarization. The D-wave phase shifts were found to be definitely needed in order to attain an adequate fit to the data. A general search for phase-shift solutions was carried out, using S-, P-, and D-wave phase shifts. One solution--of the Fermi type--was found that fits the data significantly better than any of the other solutions obtained. The calculated errors in the phase shifts of this set vary from 0.4 to 0.6 deg. Because it was felt that these errors might be deceivingly restrictive, the effects of small nuclear F-wave phase shifts on the results of the analysis were investigated and were found to be large; not only are the uncertainties in the original Fermi-type solution increased, but additional sets of phase shifts arise that fit the data well. One of these new solutions is similar to the original Fermi set except that the magnitudes of the phase shifts in this new fit are in general larger than those in the initial solution, and the signs …

This report discusses an outbreak of ruptures in January and February, 1960, which motivated serious consideration of ail phases of reactor operation so that a combined efforts to reduce rupture potential might be made. Items investigated include mixer location, gas composition control, rod movement, rod configuration, tube power, and the axial flux profile of the reactor.

This partially annotated bibliography contains 334 references from papers published from 1945 to 1959 and includes references on the consumable - and nonconsumable - electrode vacuum arc melting process. References are also given on electrode preparation, furnace construction and operation, melting, sintering, vacuum techniques, and theory.

Daily cash report for Imperial Sugar Company including a list of large withdrawals for the months surrounding the date showing the daily expenses and estimated balance for each entry. It also lists scheduled payments for bank loans.

This report is essentially an addendum, to an earlier report which presented energy loss data for various enlarged outlet fitting assemblies for possible use on the old reactors. The current report presents data for another candidate outlet fitting assembly which would tend to reduce the energy losses in the process tube outlet fittings. This outlet assembly was developed by the Materials Development Operation, IPD. The data show that the flexible connector assembly would result in a 6.9 per cent increase in normal single tube flows without modifications to existing headers or nozzles or a 13.5 per cent increase if the existing header (Parker) fittings were reamed to 0.610 inch ID. These percentages are based on comparison with the standard helical connector outlet assembly.

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Approximately five years of process improvements, and production line waste handling experience have been accumulated since the newest tank farm, 241-A, was placed into operation. Process improvements and modifications have resulted in waste volume reductions by decreasing the quantity of solids remaining in the liquid wastes from a unit of production. The resulting concentration of fission products has produced mildly boiling solutions in the storage containers permitting further waste volume reductions. Waste handling procedures have been modified to provide safe interim containment of these concentrated wastes, but restrict the usable space in existing facilities. The resulting concentration of fission products in existing facilities has a maximum heat generation rate of 10 tP 15 BTU/hour per gallon stored and the contents have a potential boiling life in excess of the anticipated life of the structure. Concentrations of fission products stored in the anticipated smaller tanks have an average heat generation 75 to 100 BTU/hour per gallon stored. A preliminary design criteria is needed as the basis for an engineering evaluation of tank design concepts to obtain maximum benefits from our operating experiences in the light of the future wastes and the Chemical Processing Department waste management program.

The reaction rate of sodium sulfite was studied as a function of oxygen concentration, Na/sub 2/SO/sub 3//O/sub 2/ ratio, temperature, catalyst, pH and surface/volume ratio.The reaction rate of hydrazine with dissolved oxygen was also studied. Oxygen removal is incomplete when the sulfite to oxygen ratio is leas than the stoichiometric quantity. With the stoichiometric quantities of oxygen and sodium sulfite present, removal is incomplete at 100 deg F in 1 min, at 200 deg F, about 95% of the oxygen is removed in 10 sec and at 300 deg F oxygen removal is essentially complete in 10 sec. With an excess of sulfite present (10 Na/sub 2/SO/sub 3//1 O/sub 2/, molar), 95% of the oxygen is removed at 100 deg F in 10 sec. At 200 and 300 deg F, oxygen removal is essentially complete in 10 sec. The rate of oxygen removal is dependent to some extent on the container material. The sulfite oxygen reaction progresses at a higher rate in boiler water than in feedwater. The reaction rate of hydrazine with oxygen is low compared with the reaction rate of sulfite and dissolved oxygen. No reduction of oxygen was noted over a one-minute period with an excess of …

Research and development are reported on the following reactors: water- cooled, EBWR, BORAX-V, sodium-cooled, EBR-1, and EBR-II. General studies were also made on nuclear superheating, reactor safety, and nuclear technology. (For preceding period see ANL-6269). (W.L.H.)

A compilation is presented of room temperature and 1200/sup o/F properties of a large number of alloys which might be considered for use in a sodium-cooled reactor. Specific consideration is given to the use of such materials as fuel cladding. The arbitrary basis for property comparison is type 304 stainless steel. The study was made of 10 classes of alloys. These alloys are alloy steels, ferritic stainless steels, austenitic stainless steels, iron and iron-aluminum alloys, precipitation-hardening stainless steels, austenitic superalloy, nickel-base alloys: cobaltbase alloys; copper-base alloys, arid refractory metals and alloys. (W.J.H.)

The handiing of interface j-ettings in waste solution processing and determination of mono-, di-, and tri-butyl phosphates in process solvents are discussed. Decontamination procedures used in ICPP are outlined. Evaporator deentrainment at ICPP is discussed. Information on Lapp pulse units and on continuous dissolution is presented. (D.L.C.)

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The needed illumination intensity is estimated from the 20-in. and 72- in. chambers to be 50 and 160 lumen-sec/ft/sup 2/ respectively. Possible source distributions are considered. With in intensity of 100 lumen-sec/ft/sup 2/ and a source brightness of 100 lumen-sec/ster. cm/sup 2/, the aperture is calculated to have a diameter of 8.6 cm. (D.L.C.)

The extent and location of corrosion, crud deposits, and defects in the ends of the 1-B heat exchanger after removing the handhole covers were determined. There was no visual evidence of pitting or corrosion inside the ends of the heat exchanger. A radiochemical analysis of a smear sample taken from the inside of number one handhole showed the presence of the following isotopes- Fe/sup 59/, Co/ sup 58/, s1>s, and Zr/sup 95/. A radiation survey performed in four handholes indicated a maximum level of 1 r/hr. (W.L.H.)

The lecture contains discussions on developments in radioastronomy, requirements for space travel to a place 12 light years away, and speculations for communicating through space. (B.O.G.)

The evolution of fission products from UO/sub 2/ during irradiation at high temperatures is of primary interest to the Gas-cooled Reactor Project. Fuel tests consisting of UO/sub 2/ pellets encapsulated in Inconel or stainless steel were irradiated in the LITR, ORR, and ETR. The capsules were pierced in hot cells, and the gases collected in evacuated systems. Fractions of this gas, of suitable activity for counting, were taken and then analyzed by gamma spectrometry. Larger fractions of gas were analyzed by mass spectrometry. Percentage of gas release varied widely, increasing with temperature, impurity content, oxygen-to-uranium ratio of the UO/sub 2/, and decreasing with bulk density. For high density, stoichiometric UO/sub 2/, the gas release was generally less than 3% up to a temperature of about 2800 deg F, about which it was greatly accelerated. Fuel burn-ups of up to 22,000 Mwd/MT were obtained. Maximum measured central fuel temperatures of 3150 deg F were reached. The lower- density nonstoichiometric UO/sub 2/ released greater amounts of fission gas, particularly Kr/sup 85/. (auth)

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; 9 < 4 6 9 7 ; 6 8 7 6 sting Deactor (MTR) has sought to develop improved, economical, long-life fuel assemblies through a comprehensive study of various fuel compositions, enrichments, claddings, burnable poisons, fuel and poison distributions, and fuelelement geometry optimization. The core materials, including uranium -- aluminum alloys, uranium oxide -aluminum cermets, thorium, thorium oxide, boron, gadolinium, dysprosium, and iridium, are tested in pilot-plant scale by irradiating them as sandwich type sample fuel plates. In the procurement of these sample plates, fabrication techniques were developed and evaluated for incorporation of all the fuels and poisons (except Ir/sub 2/O/sub 3/) into cores of aluminum or aluminum alloys. Methods were developed to minimize "dog-boning" and to produce graded fuels. Some of the sample plate compcsitions have been irradiated to high burn-up, i.e., over 50% of the U/sup 235/ content, and have operated successfully in the MTR for seven or more cycles. The irradiated uranium-- aluminum alloy and uranium oxide-- aluminum cermet fuel plates have shown excellent dimensional stability and good corrosion resistance to long-term irradiation. However, some of the thorium oxide fuel plates failed during one cycle of irradiation because of blistering, rupturing, or forming of pinholes in …

A summary of the safety precautions, operating techniques, and monitoring methods required for efficient use of the Chemical Technology Division Be facility is presented. (auth)

A test was made to determine the over-all effects of reduced coolant purification on the reactor plant. The effects were increased specific activity, gross gamma activity, and fission product activity of the reactor cooling system. (W.L.H.)

Consideration is given to the possibility that in certain types of processing or storage facilities handling enriched fissionable isotopes the pulsed neutron method can give a useful measure of the subcriticality of the system. The proposed method describes how the concentration and multiplication constant are determined for an assembly of unknown concentrations. Such measurements might be undertaken if high levels indicate the possibility of excessive concentrations of fissionable materials. Experiments were performed at the BSF in which progressively more subcritical configurations of BSR-I fuel elements were assembled. The multiplication constants were measured by the source-and-detector and pulsed-neutron methods. (B.O.G.)

Report discussing "A two-volume table for converting wavelengths in standard air to wavenumbers in vacuum. Wave-numbers are given to the nearest 0.001 K (cm^-1) for wavelengths from 2000 to 7000 A in volume 1, and 7000 A to 1000 m in volume II."