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A large number of experiments relating to nuclear structure and materialization of energy will fall within the energy range of primary and secondary particles available from the Bevatron. Some experiments of interest are outlined below with pertinent comments. Proton-proton scattering can be extended to the high energy range using liquid hydrogen targets and hydrogenous materials by bombarding the target with the internal beam or using externally scattered protons. Proton-deuteron scattering measurements using liquid deuterium targets or solid materials can also be extended. Proton scattering from heavier nuclei may be found less difficult to interpret at these level energies as the nucleons will interact more or less independently. The wavelength of the bombarding particles will now be much smaller than nucleon diameters. Nuclear collisions represent by far the most important interaction between high energy nucleons and matter. Proton-neutron charge exchange interaction within the internal target will provide an external flux of neutrons which can be used directly for total nuclear cross section measurements and neutron-proton scattering. Low energy measurements, say below 200 Mev; show that nuclear interaction cross sections do not go down as 1/{lambda} as reactions become predominantly nuclear rather than electromagnetic. Measurements can now be extended into the Bev …

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This report details activities of the Radiological Sciences Department during the 1953 Fiscal Year.

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The effects of chloride on the design and operation of a HNC/sub 3/-recovery facility are summarized. Data are presented on the concentration gradients of chloride ions in fractionators and absorbers, as well as methods for removal of chlorides to eliminate serious corrosion problems. (C.H.)

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This report gives a brief summary of work at Battelle in support of Savannah River reactor fuel elements. Barrier effectiveness tests show that 0.2 mil nickel is a minimum for diffusion barrier application. Successful bonds by roll cladding with an electrodeposited nickel bond layer have been produced without deformation of 1 inch x 1 inch x 0.180 inch cores. Deformation of core versus pack has been established for several conditions of core dimension and rolling schedule. Apparatus for a critical extrusion test is being machined. The experiment is planned for late October. Beryllium additions to the AlSi bath suppress drossing, but they have negligible effect on intermetallic compound formation. Corrosion test failures of soldered ribs sprayed with zinc took place in 6 days regardless of solder used. The same ribs sprayed with aluminum are still intact after two weeks. Solder bonding with a flash coating of copper on both core and sheath has been satisfactorily completed with aluminum and uranium.

Tests performed to determine the hazard associated with the inhalation of radioactive materials as the result of smoking with contaminated hands indicate that for dry uranium compounds adhering to the palmar surfaces of the hands, approximately 1.0% of the material may be transferred to a cigarette, and that of this approximately 0.2% may appear in the smoke which is inhaled. Most of the contamination originally placed in a cigarette was found in the ash, and only 11% of the material was not recovered following burning; approximately half of this loss may be attributed to normal losses inherent in the analytical process, the recovery efficiency for which was found by supplementary experiments to be 95%.

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Progress is preserted on studies of the Waxco process, new raw materials, high (NH/sub 4/)/sub 2/Csub 2/O/sub 4/ insoluble in MCW UF/su b 4/, recovery of HF and U from MgF/sub 2/ bomb slag, study of U metal with respect to metal quality, C contamination in cast U, vacuum fusion 0 determination, pyroelectric con centration methods for improving B sensitivity, grinding sample preparations for spectrographic analysis, and determination of N in U metal. (For preceding report see NYO-1353). (M.C.G.)

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The applicability and refinement of various procedures for the treatment and digestion of C-slags and other uraniferous residues for recovery of U values were studied. The recovery of U from BFC-6 was investigated, placing emphasis on procedures which will not chemically alter the Cu and Sn media. Methods of U recovery from various residues resulting from Na/sub 2/CO/sub 3/ digestion of miscellaneous U-bearing materials, to reduce the U/sub 3/C/sub 8/ content below 0.05%, are discussed. (W.L.H.)

Power Breeder Reactor. Conceptual design studies for the Power Breeder Reactor indicate the feasibility of a contained primary coolant system in a package arrangement. One- and two-group calculations are presented in detail for preliminary PBR estimations. A technique for impregnating UO/sub 2/ with NaK has been developed. The resulting putty-type fuel was successfully extruded tbrough a 3/8-in. hole. Data are presented on the fuel element design factors imposed by heat transfer and cooling limitations for fuel plates, pins, and spheres. Fission heat liberated in the PBR blanket was estimated to be 7.7% of the total core power. Design criteria resulting from this estimate are analyzed. Heat exchanger size for the transfer of 500 Mw of heat from Na to NaK has been calculated for the intermediate exchanger and for the NaK-toH/sub 2/O steam generator. A theoretical treatment is presented for the thermal stress analysis of stainless steel-clad U fuel plates. Boiling Reactor Heat Transfer Experiments. Further results have been obtained from natural-circulation boiling-density tests and investigations of natural-circulation flow rates. A special thermocouple design, meeting the rapid-response requirements of high-power plate transients, is described. Feasibility studies on heavy water boiling reactors are presented for spherical boiler, pressurized tube, and horizontal …