Report covering progress regarding a study on radiation synthesis involving halogenated compounds. Experimental progress, results and discussion are included.

From summary: The design of a spectrometer with the requisite improvement in crystals facilitates X-ray tube fluorescence.

An investigation of the emission spectrum from radiation-daniaged xylene led to the conclusion that no gross corrections are needed for xylene when used as a scintillation solvent. Data are included from measurements of nonradioactive energy transfer in p-xylene and diphenyloxazole organic scintillation solutions. Measurements were made of the energy resolution of a twinscintillation fast neutron spectrometer. Accurate values of electron drift velocity in purified noble gases and nitrogen were obtained by measuring the transit time of photoelectrons across the gap of a parallel-plate condenser. Information concerning the transport collision cross section of low-energy electrons on noble gases was obtained from drift-velocity data. A method is discussed for the determination of traces of Freon-12 by positive ion emission techniques. Data are reported from late observations of the distribution of radium in the human body; the microscopic distribution of the dose in the skeleton arising from deposited calcium-45, strontium90, and radium-226 as measured autoradiographically; and determinations of individual alpha emitters in mixtures of alpha emitters. Data are tabulated from measurements of gross fission product radioactivity in air samples and in samples of soils collected from August through November 1959. The soil and air fall-out data are discussed. Measurements were made of the …

Construction of the NUMEC Plutonium Facility was essentially completed. Methods for the preparation of Pu, U, and Th oxides of high purity and the fabrication of these materials into fuel shapes is discussed. (For preceding period see NUMEC-P-10.) (W.L.H.)

Thermal stress testing was performed on two fuel plates, one cut from a brazed SM-1 dummy fuel element and the other from a TIG Welded SM-2 reference element. The test specimens were subjected to transverse temperature differences of up to 200 deg F, and distortion and strain at various locations were measured. The effect of the thermal stress was to increase the amplitude of original distortions. Adddtional distortions due to thermal stress were proportional to temperature differential and to ripple length. Tensile stresses in the side plate sections were measured as approximately 10,000 psi at maximum reactor temperature difference. Individual weld loadings in shear were measured as 38 lb per weld. Results of the tests were considered inconclusive because of unrepresentative initial plate distortion. (M.C.G.)

Abstracts were prepared on 26 of 28 papers presented at the Conference on the Physics of Breeding held at Argonne National Laboratory on October 19 to 21, 1959. (C.J.G.)

Direct recording of nuclear pulse height data on magnetic tape is being investigated. The characteristics of various brands of commercial tape are being investigated and a waveform analysis is being performed in an attempt to determine the most favorable frequency range for available tapes. Use of the magnetic modulator head is being investigated to minimize variations due to short term tape speed variations. (W.L.H.)

>The materials and methods used for the long-term nuclide pairs are essentially the same as those previously described. (April - June Report). The split planchet method was used to determine the resolving time of the tracerlab superscalar counting apparatus which is currently in use. A planchet was split in two and a sample of nuclide placed in each half and counted. From these results a formula for calculating true counting rates was evolved. Data on resolving time loss for the Superscalar are tabulated. Transmission values of Sr/ sup 89/- Ct/sup 14/ mixture were measured to determine the degree to which error in these values can be reduced by long counting periods. Data on P/sup 32/ and C/ sup 14/ tagged rubber age counts are tabulated. Also, rubber samples were prepared by adding Ca/sup 45/, Cl/sup 36/, Nb/sup 95/, and T c/sup 99/, mixing and vulcanizing and isotope pairs (Ca/sup 45/- Cl/sup 36/ and Nb/sup 99/-Tc/sup 99/) were similarly incorporated in other samples. Ground and suspended samples of these preparations were age counted. The results obtained by incorporating radioisotopes into rubber can not show close correlation between observed and calculated time. Probable reasons for errors and inconsistencies are discussed along with …

The third quarter of 1959 was occupied with putting the finishing touches on components of the Two-Way Model, adjusting the magnetic field to the required magnitude at all points, and life testing completed components. The present status of the model components is given including the magnet, vacuum tank, equipment for acceleration, and injector. Status of various study groups is discussed. A list of papers published, submitted for publication, and presented at meetings for the period Oct. 1958 to Oct. 1959 is given. (W.D.M.)

The papers prepared and presented by the Atomic Energy Commission and Contractor Personnel are presented. The meeting covered a broad range of problems encountered in the AEC and SS Materials Management work. (W.L.H.)

Preliminary engineering studies have indicated the need for modifications and improvements to the reactor coolant backup systems of the old areas in order to provide adequate safety of operation at power levels programmed for the future. These evaluations of the coolant backup systems were based on the recently adopted reactor cooling safety criteria. It was concluded that the secondary coolant systems would be adequate in capacity and reliability for the proposed future operating conditions except for certain cases of natural disaster such as earthquake damage. It was concluded that the last ditch coolant systems would be inadequate for the proposed future reactor operating conditions. The purpose of this report is to define the scope of modifications and improvements required to provide adequate last ditch systems in the old areas for future operating conditions as proposed by the Reactor Modification Program. Irradiation Processing Department, Fiscal Years 1961 through 1966. Adequate last ditch cooling will be provided for the 100-K Areas under Project CGI-844 which is currently in progress. The results of this study provide a basis for future budgeting action and project planning.

Chemical-Metalluaical Processing. A direct-cycle fuelreprocessing plant using pyrometallurgical procedures is being designed as part of the Experimental Breeder Reactor No. II project. The reduction of uranium oxide was investigated, using pure Mg and solntions of Mg in Zn and Cd. Cadinium solntions of U were shown to be stable in Types 405 and 410 stainless steel containers at temperatures up to 550 deg C. The liquid metal corrosion loop in which a U-Mg--Cd alloy is being circulated at 550 deg C has been in trouble-free operation for 3000 hrs. Recovery of Pu from Mg solution by distillation of Mg was demonstrated on 1-g Pu scale. The solubility of Th in liquid Cd was measured over the temperature range from 1.9 x 10/sup -3/ per cent at 348 deg C to 1.8 x 10/sup -2/ per cent at 658 deg C. The solubility of Mn in liquid Cd was found to range from 0.27% at 414 deg C to 1.43% at 661 deg C. The solubility of Ni in liquid Cd was measured. The partition of U between liquid Al and liquid Cd was studied as a function of U concentration. The reaction of Al with a liquid Cd solution containing …

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Techniques for improving stability of scintillation counter chopper systems and their development for use in industrial control applications are being investigated. Tests are being performed to determine the causes of fluctuations. An integration and frequency converter is being developed in which the anode current of the photomultiplier tube is alternately switched between two integrating condensers by action of a commutator switch. The voltages developed across the two condensers are proportional to the respective intensities of the two radiation beams seen by the scintillation counter. Slective sampling by the use of Loss filters is scheduled for future investigations and a literature search on counter stabilization is also planned. (J.R.D.)

Progress is reported in corrosion studies of stainless steels, Nb, Zr, Al- Fe-Mo, Mo, Ni alloys, and Al- Ni by various materials including Na, Na-K, Li, Rb, and fused salts, Corrosion studies in pump loops of various materials by fused salts and liquid metals are reported, Fuel elements and shielding materials for ART and APPR are beirg developed. General studies in welding and brazing, nondestructive testing, fabrication, and inspection are described. Developments in high-temperature metals and ceramics, metallographic techniques, ceramic materials, and Zr alloys are reported, (T.R.H.)

ABS>Fuel Element Research and Development. Dynamic and static corrosion tests on 8001 Al were completed. Annealmmmg of 1100 cladding on 5083 and M400 cladding on X2219 were tested at 500 deg C, and investigation continued on producing X8101 Al alloy cladding in tube plates by extrusion. Boiler fuel element capsule irradiation tests and subassembly tests are described Heat transfer loop studies and fuel fabrication for the critical facility are reported. Boiler fuel element mechanical design and testing progress is desc ribed. and the superheater fuel element temperature evaluating routine is discussed. Low- enrichment superheater fuel element development included design studies and stainless steel powder and UO/sub 2/ powder fabrication studies Reactor Mechanical Studies. Research is reported on vessel and structure design, fabrication, and testing, recirculation system design, steam separator tests, and control rod studies. Nuclear Analysis. Reactor physics studies are reported on nuclear constants, baffle plate analysis, comparison of core representations, delayed neutron fraction. and shielding analysis of the reactor building. Reactor and system dynamics and critical experiments were also studied. Chemistry. Progress is reported on recombiner. radioactive gas removal and storage, ion exchanger and radiochemical processing. (For preceding period see ACNP-5915.) (T.R.H.)

Progress in development of a nuclear density gage for use in thickness and density measurements is reported. A Ross filter system for energy discrimination in the alpha ray region was constructed. Soller slits for collimating the radiation entering and leaving the filters so that a constant absorber thickness is seen by the radiation beam is under construction. Comments by visiting Russian scientists on the density gage and a discussion of their work in this area are included. (J.R.D.)

A summary of each computer program initiated during the report period together with code symbols indicating the extent to which information concerning the program is readily available are given. Programs previously reported are included if changes were made or additional information concerning them was placed in the program library. Abstracts of 704 newsletters and GEORGE bulletins are presented. (For preceding period see ANL-6089.) (W.D.M.)

The rate of reaction of highly irradiated U with air, CO/sub 2/, and steam was studied in sn investigation of the fission product release potential in a loss-of-coolant type accident postulated for Pu-producing reactors. Highly irradiated U was found to be more reactive, probably because of the defects in the oxide coating formed by the inclusion of fission products. Complete oxidation or melting was found to release rare gases, I, and Te semi- quantitatively in most atmospheres. Other fission products (Ru, Cs, and Sr) were released to a lesser extent and apparently in proportion to the amount of self- heating induced. In order of their relative tendency to release fission products, the atmospheric conditions investigated were rated in the order: air > CO/sub 2/ > steam. (auth)

The papers presented at the meeting were recorded and transcripts are given along with the discussion which followed each paper. Separate abstracts were prepared for 12 of the 13 papers presented. (W.D.M.)

Fluoride Volatilization Separations Process. Development of a fused fluoride process for dissolution of uranium-- zirconium fuel alloys continued. In corrosion tests to find a suitable container material, Ni was found to be susceptible to a sulfur-type attack. Hastelloy B showed promise, and graphite offers excellent chemical resistance but poor mechanical strength. The dissolution rate of Zr in NaF-- ZrF as affected by impingement of the HF sparge was studied. Production of UF/sub 6/ by fluidized bed fluorination of UF/sub 4/ from ore concentrates was studied. The preparation, melting point, vapor pressure, and vapor density of UF/sub 5/ are given. Preliminary dissolution and recovery runs in semi-works equipment are discussed. Fluidization. Fluidized- bed techniques have been applied to conversion of UO/sub 2/(NO/sub 3/)/sub 2/ to UF/sub 4/ and to calcination of radioactive liquid wastes. Activities of the Green Salt Pilot Plant and shakedown runs of the shielded waste calciner are described. Reactor Chemistry. Studies continued on the kinetics and mechanism of oxidation of U, Th, and Zr. Data are given for oxidation of U in oxygen from 125 to 295 tained C and 20 to 800 mm pressure, and for Zr from 400 to 900 tained C and 200 nan O/sub …

Three methods for the determination of radium were evaluated. In two methods, the radium is finally precipitated with barium sulfate as carrier and alpha-counted. In the other method, the radium is recovered in a carrierfree condition for alpha counting. A method for determining radium by removing interfering elements with solvent extraction technniques and precipitating the radium with barium sulfate is described. A method which gives a rapid estimation of radium isotopic composition in samples, based on precipitation with barium sulfate, conversion to the carbonate, and alpha counting, is described. Flowsheets are contained on all five processes discussed. Two processes for the determination of thorium were evaluated. One method consists essentially of extraction of carrierfree thorium in TTA-benzene, stripped in nitric acid, and direct plating of the nitric acid solution for counting. The second method consists of thorium precipitation on lanthanum hydroxide, then on lanthanum fluoride, dissolution in nitric acid aluminum nitrate, thorium extraction into TTA solution, stripping into nitric acid, and counting. Flowsheets for the processes are given. The effects of pH, sulfate ion concentration, calcium and other contaminants, and temperature on the adsorption of radium from acid leach liquors by barite were studied. Coprecipitation studies of radium with barium …

With the project design work virtually complete, progress during the quarter consisted primarily of prccurement, fabrication of components, and construction at the reactor site. Developments are briefly summarized in the fuel element program, core physics vessel and internal components, control rods and rod drives, shielding, process, instrumentation, building and facilities, and construction. (For preceding period see ACNP-ERR-5.) (W.D.M.)