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The basic design and development concepts are presented on a six vane air motor intended for use at elevated temperatures. (auth)

Photograph used for a story in the Daily Oklahoman newspaper. Caption: "We can't handle science apart form all the rest of human learning."

Photograph used for a story in the Daily Oklahoman newspaper. Caption: "James Gindling Harlow is a brainy, round-faced man who doesn't get panicky about crises in education."

Photograph used for a story in the Daily Oklahoman newspaper. Caption: "A whole lot of people here are going places and doing things . . . l like to be among them."

Weekly newspaper from Bellaire, Texas that includes local, state, and national news along with advertising.

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.

The economiics and physics of four schemes of pIutonium recycle in the Calder Hall type reactor are considered. The four possible schemes are: (I) to blend the Pu produced In a run with fresh naturaI U for a subsequeut run; (2) to alloy the Pu with somie diIuent metal and fabricate the alloy Into high heat- transfer elements morc like MIR or PWR-sced type elements and"spike' a subsequent load of fresh natural U elemients with these Pu elemicnts; (3) to recycle half the spent U as well as the Pu; and (4) to thke advantage of the extra reactivity gained fromi the recyeIed Pu to deerease the Iattice spacIng, thereby increasing the conversion ratio with the hope of increasirg the attaInabIe exposure. It was concluded that schcme (1) is the miost economiical. (W.D.M.)

A series of reactor frequency response measurements, relating flux or power level to a reactivity input function, were made to evaluate reactor stability for different values of power parameters. These parameters included: power level, steam pressure, and control rod position. The results were extrapolated to predict EBWR stability at higher operating powers. The experimental data may also be used to evaluate the thermodynamic and hydraulic constants. (authl

The elementary sieps in the photolysis of liquid ethyl iodide by light of wavelength 2537 A by determining initial rates of iodine production in the presence.of added iodine and hydrogen iodide were analyzed at 25 and --70 d C to get information on the activation energies of competing elementary reaciions. Investigations were also made of the effects of additives on the photolysis of glassy ethyl iodide at --180 d C, and evidence for the formation of trapped radicals during photolysis and radiolysis of the solid was sought by electron paramagnetic resonance measurements. (J.R.D.)

Irradiations were made on a number of uranium-plutonium alloy specimens made from both cast and extruded materials. The cast alloys included alloys of uranium with 3.7, 5.6, and 13.0 wt. % plutonium, and the extruded alloys included alloys of uranium with 9.5, 14.1, and 15.7 wt.% plutonium. One-half of the extruded specimens were given a heat treatment consisting of heating to 545 deg C and cooling to and holding at 500 deg C for one hour in an attempt to remove the preferred orientation that was anticipated from extrusion. The specimens were irradiated to burnups ranging up to 0.54 at. % with central temperatures ranging up to 490 deg C. The cast specimens were all found to have developed severe surface roughening as a result of the irradiation they received, presumably because of excessively large grain sizes present before irradiation. Identically fabricated unalloyed uranium specimens showed similar behavior. The as-extruded alloy specimens maintained good surface smoothness under irradiation, but showed elongations which were dependent on plutonium content. For example, in samples with 0.4 at.% burnup, a 14.1 wt.% plutonium alloy specimen elongated 96%, whereas an 18.7 wt. % plutonium alloy specimen elongated only 5.4%. The heat-treated extruded specimens did not …

The exposure-time for fission fragment catcher foils, used in nuclear reactor power mapping, was arbitrarily set at 20 minutes. Work performed to evaluate this choice and to attempt an optimization of the exposure time is reported. A true optimum was not found. Forty minute runs are suggested, however, as a practical optimization and as an alternative to the 20 minute runs in current usage. (auth)

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The oxidation of ferrous sulfate is used as the method of measurement of radiation intensity in the Argonne National Laboratory's High-Level-Gamma Food Irradiation Facility. The preparation and calibration of the dosimeters are described and illustrated photcgraphically. (C.H.)

For presentation at the 1958 Nuclear Congress, Nuclear Science and Engineering Conference, March 17The experimental program was focused on the problems of containing the Na, of providing a barrier material with low neutron absorption cross section and an ability to withstand the action of hot Na, of developing an arrangement of this material which is mechanically adequate, and of demonstrating that an integrated barrier system can be safety operated under reactor tempernture and pressure conditions. Possible barrier materials were subjected to hot Na jets. Stainless steel, Zr, and Al withstood the jet very well- The experimental arrangements of other tests are shown. (M-H-R-)

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Catalog number 58, containing information concerning remote maintenance tools which have been used at ORNL, is presented. It is intended as a guide and as a starting point for modification work. Complete information is not available on all tools. (J.R.D.)

Each Borax-lIl fuel subassembly consists of a group of aluminum-clad aluminum-uranium alloy fuel plates arranged in an MTR-type array. The fuel plates are electric-resistance spot-welded to two aluminum sideplates and an aluminum central-support plate. An anuminum-0.6 wt.% boron, burnable poison strip is attached to each fuel subassembly. The poison strips are made by hot extruding a mixture of aluminum and elemental boron powders in the desired proportions. (auth)

Originally intended for publication as NNES-VIII-7. Elghty-one papers are presented on thc chemistry of uranium. (W.L.H.) 13236(Abstract unscannable)

This compilation of reactor physics constants, based on data available up to March 15, 1958, is the first publication of the Reactor Physics Constants Center (RPCC). The primary objective of the RPCC is the periodic compilation of the latest and best values of the constants, recipes, formulas, etc., which are necessary to calculate reactor characteristics. (W. D.M.)

A revitew is presented of pretreatment methods with special attention to those useful at Eurochemic. Mechanical and chemitcal decanning methods presently in use or proposed for Al-, Mg-, stainiless steel-, and Zror Zr alloy-jacketed fuels are discussed. Darex, Sulfex, and Zirflex processes are included along with special methods ror U-- Mo and U- Zr fuels. (T.R.H.)

The stress-strain properties of the APDA reference alloy of uranium- 10 wt.% molybdenum at various burnups up to 2.1 total at. % are described. Data were ob tained on both irradiated and unirradiated specimens of the alloy by the use of a remotely operated bend-testing machine. Tensile properties of unirradiated material are also reported for comparison with data obtained from the bend tests. The mathematical procedure used in obtainirg equivalent uniaxial stress-strain properties from the bend-test data is described in the Appendix. The results of the bend tests indicate that the physical properties of the reference alloy were severely affected by irradiation to burnups as high as 2.1 total at.%. At a test temperature of 500 deg C, the modulus of elasticity, ultimate strength, and strain at fracture decreased rapidly up to a burnup of about 0.5 to 1.0 total at.% with the rate of change decreasing thereafter. No important differences were noted between coextruded and hot-rolled material. An indication was obtained that the ultimate strength of the alloy was improved with increasing irradiation temperatures up to about 500 deg C. Data obainined on unirradiated material indicated that ductility of the reference alloy was lower at 500 deg C than …

List of engineers employed in the 11th District of the Missouri-Kansas-Texas Railroad South Texas Division as of January 1958. It includes the name of each person and employment date, with the most senior person listed first.

List of firemen employed in the 11th District of the Missouri-Kansas-Texas Railroad South Texas Division as of January 1958. It includes the name of each person and employment date, with the most senior person listed first.