An ionization-type alpha counter is used to mensure the uniformity of thin coatings of alpha -emitting materials to plus or minus l% exclusive of statistical error. The (n, alpha ) reaction allows the counter to be used for measuring the uniformity of B/sup 10/ foils when a suitable neutron source is provided. (auth)

Twenty-nine references to published literature articles and reports on preparation, color reactions, and analytical uses of 2- (2-hydroxy-3,6-disulfo- 1naphthylazo)-benzenearsonic acid are given (T.R.H.)

"Expressions are found to relate DELTA gamma to the n-errors.'' It is demonstrated that the integral n-value concept'' is of no use in the present case. A modification of integrated n-value'' is suggested."

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The two most important considerations in the disposal of radioactive wastes are safety and economy. All other steps in the waste disposal complex must be tuned to accomplish these two goals. In general, the hazardous waste in the nuclear power complex affect the cost of the nuclear power reactor fuel cycle, the general environment since disposal must exclude radioactivity from the environment for over 500 years, the costs and/or methods of waste treatment including fission product utilization, the methods of shipping, the location of chemical processing plants and waste disposal sites, the methods of disposal best suited for a particular type of waste or site location, and potential public damage and third-party liability.

The effect of deuterium oxide (D{sub 2}O) on the survival of mice inoculated with Ehrlich's mouse ascites tumor has been studied. Mice maintained on 25% and 30% D{sub 2}O drinking water showed an improved survival time of about 6 days whereas 40% D{sub 2}O drinking water had no effect on survival time. The effect is interpreted in terms of inhibition of tumor cell division and systemic toxicity.

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The development of a fast breeder fuel cycle based on a core fuel consisting of mixed dioxides of uranium and plutonium is described. Process flowsheets, material balances, operating schedules, cost schedules, and a plant layout are presented, and the laboratory- and plant-scale process and equipment demonstrations are described. A cost estimate based on a demonstration of the process including the unique plant equipment gives a total fuel cycle cost of 2.04 mils/kw-hr and a net fuel cycle cost of 1.53 mils/kw-hr (0.3 breeding gain assumed). (auth)

The thermal cycling, irradiation behavior, and fabrication characteristics of U are strongly dependent upon grain size; a smaller grain size yields the better properties. Grain refinement of cast U may be accomplished either by hot working in the high alpha temperature range or by heat treatment; refinement by the latter method was the object of this investigation. The variables studied were time, temperature, specimen size, multiple quenching, and alphaannealing after quenching. The results of the investigation have led to the following conclusions, within the scope of the experimental conditions. The grain size of cast U may be appreciably refined by beta-quenching. Time and temperature in the beta phase are not significant in determining the final alpha grain size. Multiple beta-quenches (two to four times) produce better grain size refinement than a single quench. Alpha-annealing after beta-quenching causes recrystallization, but does not greatly affect the grain size. Gamma-quenching is not recommended as a practical heat treatment. (auth)

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Data are presented on the mechanical properties of iron-silicon and iron- aluminum alloys in the range 0 to 14% Si and about 8% aluminum. The effect of third elements on ductility is discussed, and data are prcsented which indicate that it is not possible to obtain a disordered structure in Fe--Si a1loys from 8 to 14% Si. It is concluded that alloys of iron with 6 to 8% aluminum offer a promising base composition for development of low neutron cross section alloys for use in nuclear reactors. (auth)

The luminescence of various chlorophyll-containing plant materials has been investigated under a variety of conditions. The results have been shown to be consistent with a mechanism involving the recombination of electrons and holes trapped in a quasi-crystalline lattice. Some details of such a mechanism have been proposed which suggest the mode of entry of the light energy into the photosynthetic pathway.

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A method is described for routine urinalysis for Po by plating on copper at room temperature from acid solution. A discussion is presented based on experience gained by this laboratory in working with the method over a four-year period. (auth)

Powder dispersions of titanium--boron and titanium-boron carbide were prepared, clad, and evaluated for use as control materials. Compacts possessing up to 95 per cent of theoretical density were prepared by a hot-pressing technique. The relatively low temperatare of 1500 deg F was used to obtain the desired high density. There was no visible reaction between the boron dispersant and titanium. Excellent metallurgical cladding of the titanium-- boron dispersion with titanium was achieved by the use of both rollbonding and gas pressure-bending techniques. The rolling was performed at 1500 deg F and the pressure bonding was accomplished at 1600 deg F with a helium pressure of 10,000 psi for a time of 6 hr. The pressure-bonding technique produced a specimen with a more uniform boron dispersion and a better high-temperatare-water corrosion resistance than were obtained through roll bonding. Extruded titanium--boron dispersions were joined to hafnium and clad with Zircaloy-2 by a roll-bonding technique to determine in a preliminary way the feasibility of preparing clad composite control rods. Strong, relatively ductile bonds were obtained between all of the components by the rollbonding process and postfabrication heat treatment. (auth)

Progress is reported on the following studies: development of materials for Hanford reactors, developments for Al-clad fuel elements, studies of Zr-U alloys, corrosion studies of Zr, reactor-materials development, physical metallurgy, corrosion problems associated with the recovery of spent reactor fuel elements, evaluation of a reflector-controlled heterogeneous boiling reactor, studies of Na-Ta compatibility at elevated temperatures, and de velopment studies for the PWR. (For preceding period see BMI-1189.) (W.L.H.)

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ABS>Progress is reported in the following studies: the autoradiographic mapping of the deposition of Ca/sup 45/ in cortical bone in dogs; measurement of fission-product activity present in soil; factors affecting the performance of ionization chambers; calibration tests on the dibutyl phosphate method of isolating Th/sup 228/ from solutions of ashed bone; microradiographic demonstration of changes in mineral density in dog bones; radiometric determination of radon in bone and in the atmosphere; changes produced in xylene by exposure to massive doses of Co/sup 60/ gamma radiation; applications of the human spectrometer in in vivo measurements of Cs/sup 137/ build-up in humans; determinations of Cs/sup 137/ atmospheric content as a function of time; development of a tracer method using K/sup 42/ for measurement of exchangeable potassium in humans; determinations of the radium body burdens in fornner dial painters; and the atmospheric diffusion of stack particles. A meteorological model towing tank is described which was constructed as an alternative to a wind tunnel for model studies of atmospheric turbulent diffusion. Preliminary studies employing the apparatus are described. (For preceding period see ANL-5679.) (C.H.)

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One amorphous and three crystalline polymorphic modlfications of UO/sub 3/ have been prepared by pyrolysis of uranyl nitrate hexahydrate. The hydration reactivity of UO/sub 3/ appears to be a function of its residual N content which is, in turn, dependent on the method, time, and temperatuee of denitration. Amorphous UO/sub 3/ is more reactive than crystalline UO/sub 3/. The initial oxidation reactivity (the O/sub 2/ sorption in 1 day at room temperature) of UO/ sub 2/ varies with the method of preparation of the UO/sub 2/. The average oxidation rate of UO/sub 2/Z after the first day decreases with increasing N content of the UO/sub 3/ from which the UC/sub 2/ was made. If soluble nitrates are removed from UO/sub 3/ by water leaching prior to reduction, the final reoxidation reactivity of the UO/sub 2/ is increased by a factor of 10. Hydration and dehydration of amomphous UO/sub 3/, without leaching, decrease the final reoxidation reactivity of the subsequent UO/sub 2/ by a factor of 10. UO/ sub 2/ made from amorphous UO/sub 3/ has a higher reoxidation reactivity than when made from crystalline UO/sub 3/ of the same N content. (auth)

Report presenting a collection of gamma spectra containing samples of the response of NaI(TI) scintillation detectors to a large number of the more frequently encountered radioactive nuclides.

Radioactive contamination was confined and controlled in an isolation tank when irradiated plates of natural U were cut under water. (auth)