This is the monthly report for the Hanford Laboratories Operation, May 1958. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, physics and instrumentation research, employee relations, operations research and synthesis operation, programming, radiation protection, and laboratory auxiliaries operation area discussed.

This is the monthly report for the Hanford Laboratories Operation, May, 1959. Reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, biology operation, physics and instrumentation research, employee relations, operations research and synthesis operation, programming, radiation protection, and laboratory auxiliaries operation area discussed.

Knowledge has developed steadily over the past 18 months toward defining the characteristics of the gamma and neutron radiation associated with plutonium and its compounds. Laboratory measurement have been made on plutonium samples taken from the RMA Line, film badge studies have been made in plutonium processing areas, and calculations have been made predicting dose rates and shielding requirements at higher plutonium exposure levels. As these studies continue, and more precise data is accumulated, it will be possible to (1) more accurately evaluate the radiation received by operating personnel, and (2) more accurately (and economically) specify shielding for facilities designed for processing high exposure plutonium. This report gives the results of a gamma energy analysis of the RMA Line and Recuplex obtained with a laboratory model gamma spectrometer. Measurements have been made in the 234-5 Building which have defined the general gamma energy spectrum emitted by the plutonium processing hoods on the RMA Line and in Recuplex. The data obtained from this study has helped resolve the discrepancy between laboratory data and film badge data, and has provided additional information to help in prediction of the gamma radiation levels to be expected from plutonium irradiated to 2000 MWD/T (NPR) and …

Atomic Energy Commission has expressed interest in obtaining xenon with a composite neutron absorption cross section of less than one barn. This material may be obtainable from the off-gas of the Purex dissolver. A proposed gas purification facility would process the Purex off-gas through two distillation steps for isolation of a ``rough`` cut of xenon isotopes containing principally Xe{sup 131}, Xe{sup 132}, Xe{sup 134}, Xe{sup 136}, and a small quantity of krypton. This material would become the feed stream for a thermal diffusion plant for xenon isotope separation. Thermal diffusion has been shown to be the most economical way to concentrate the two heavier xenon isotopes of low cross section and to reject the krypton along with lighter xenon isotopes of high cross section. The objective of the work herein reported was to provide the basis for (l) a scope design of pilot thermal diffusion equipment and (2) design of experiments to be made with this equipment. In the absence of experimental data, the pilot design was developed from theoretical considerations of the parameters considered important in thermal diffusion column operations. It was assumed that the pilot unit would have to provide information on the correlation of theory with practice …

The Facilities Engineering Operation of the Chemical Processing Department prepared a process study scope design of a large thermal diffusion plant for xenon isotope separation. This scoping was done perforce on the basis of calculations made from exclusively theoretical considerations because actual design data are not available. The designers are of the opinion, however, that, such a basis is not adequate to justify the construction of the plant and have, therefore, requested that an appropriate supporting research and development program be carried out. This report presents an experimental plan for obtaining the data required. Anticipated results from the proposed experiments as outlined below, are expected to be useful for determining the correlation of thermal diffusion column theory with practice for this particular system of xenon isotopes. An interpretation of the data will permit the determination of the sensitivity of the column parameters to the change in operational and design variables over which the designer and operator have control. Basic observations made on the behavior of xenon may, in addition, be of general scientific and technological interest. Included in the report are estimates of the kind and quantity of data to be obtained, the analytical services required, and the total analytical …

This paper presents a scope design of two coaxial type thermal diffusion columns. These experimental columns are proposed to meet the requirements of the research and development program given in Part 2 of this report series. They would rearrange the isotopes of xenon from the Case II product of the Purex Gas Separations Facility to yield a product with a composite neutron absorption cross section of less than one barn. The theoretical basis for the design is given in Part 1. The auxiliary equipment necessary for the operation and control of the columns is described in Part 4. Major components of the columns and their functions are described in this part, The proposals for the materials of construction and the heating systems are not conclusive. Several possibilities for these requirements, however, are included. The design of two experimental thermal diffusion columns is given to meet the needs of a proposed research and development program for rearranging the isotopes of xenon. The proposed columns are six meters in length and have a maximum diameter of about five inches. They could be built at Hanford for an estimated cost of $10,000.

None

Slag and crucible can be dissolved satisfactorily by the Los Alamos method of total dissolution with nitric acid in the presence of aluminum nitrate. Extraction of 99% of the plutonium from total dissolution salted with aluminum nitrate was achieved by three successive contactings with 1/10 volumes of 30% TBp- AMSCO 125-90W. The TBPAMSCO phases contacted with leaching solutions salted with calcium nitrate must be scrubbed to remove calcium. Stripping with three 1/10 volumes of 0.1M hydroxylamine sulfate removes 99% of the plutonium from the 30% TBPAMSCO, initially O.lM HNO/sub 3/. Plutonium(III) oxalate, (which could be blended into 234-5 operations) can be precipitated from the aqueous strip solution. It is chemically feasible to recycle slag and crucible solution to the Redox IIA column in amounts up to at least lO% of IIAF by volume. It is also chemically feasible to recycle nitric acid solution of slag crucible obtained in the presence of aluminum nitrate to the Product Precipitation step of the Second Decontamination Cycle of the Bismuth Phosphate Process. (auth)

None

A second set of quadrupole magnets was installed in the cyclotron close to the vacuum chamber in order to increase the beam intensity. The pole pieces of the 20in. analyzing magnet were trimmed. Scattering of 19Mev alpha particles by C/sup 12/, 0/sup 16/, and S/sup 32/ was investigated at various angles. Beta- gamma directional correlations of allowed as well as forbidden beta transitions in the decay of Na/sup 24/, Co/sup 60/, and Sc/sup 46/ were investigated. Results of an experimental investigation of the beta-gamma directional correlation and the spectral shape of the first-forbidden spectra of K/sup 42/ and Au/sup 198/ are presented. Polarization-directional correlation measurements were performed on the Ar/sup 38/ cascade gamma rays following Cl/sup 38/ decay in order to determine the parities of the levels and to remove some of the ambiguity of the directional correlation spin assignments. Nonconservation of parity in beta decay, circular polarization of gamma rays following beta decay, and polarization of conversion electrons following beta decay are considered. The transverse polarization of beta particles in the first-forbidden beta decay of Au/ sup 198/ was measured. A 4 pi beta spectrometer for the study of beta and gamma radiations associated with the decay of short-lived …

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 …

None

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.)

The ''absolute'' containment of ions in the DCX magnetic mirror field resulting from the cylindrical symmetry of the field is discussed. The regions of confine;, ment in space and momentum are plotted for 300-kev deuterons. (auth)

None

None

A twenty-inch analyzing magnet has been completed except for the final trimming of the pole pieces. In onder to further examine the systematics in the angular distribution of elastically scattered alpha particles, the scattering of alpha particles from spectroscopically pure O/sup 16/ and hydrogen sulfide gases was studied. The change of the static quadrupole interaction in indium metal wth temperature was investigated. Results give a value Q = 10/sup -24/ cm/sup 2/. An experimental study of the betagamma directional correlations in the decay of Au/sup 198/, he long-range as well as the short-range stabilily of the fast coinci-dence scintillation spectrometer has been improved by building new 404A limiter circuits. The directional correlation of the 172 to 247 kev gamma cascade of Cd/sup 111/ was measured for gaseous InCl/sub 3/ sources as a function of the delay introduced into the channel accepting the first gamma ray of the cascade, and also as a function of the source temperature and pressure. This was done in an attempt to determine the nature of the interaction to which the Cd/sup 111/ nucleus is subjected when the source is in the gaseous state. In the decay of Cl/sup 40/ there is evidence for gamma rays …

In the reaction of silicon halides with graphite to form silicon carbide, thermodynamic conditions were determined for the formation of SiC, free of elemental silicon. The use of these conditions was designed to limit the rate of coating formation by the rate of diffusion of carbon through the coating, and render the operation independent of the vapor-flow factors which normally limit the uniformity of vapor-deposited coatings. Although a wide range of pressure- temperaturecomposition conditions was explored, it was not possible to duplicate the success previously obtained in applying the method to NbC, TaC, TiC, and ZrC coatings. Fundamental differences in the characteristics of the carbides which may account for the difference in behavior are the lack of a range of homogeneity in beta SiC crystal structure, and the fact that SiC undergoes a modification from the cubic beta to a hexagonal form at l900 to 2000 deg C.There remains the prospect of forming a uniform SiC ''sponge'' by the present process which can be subsequently impregnated with metallic silicon to form an oxidation-resistant cpating. (auth) l6200 Preliminary results were obtained on the value that commercially pure Pu (95% Pu/sub 235/ and 5% Pu/subp 240/) has when used as nuclear fuel. …

This is the monthly report for the Hanford Laboratories Operation, May, 1957. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.

None

This document has been written because of a request for information from the Advisory Committee on Reactor Safeguards. Hanford operating experience has been summarized in terms of operating hours, startups and scram analysis.

None

Progress is reported on the development of a cyclone which will remove particles larger than 8 microns. A method is proposed for a more efficient separation of particles by increasing the number of size separation filters in the sampling train. Preliminary tests with submicron polystyrene particles are being conducted. Numerous methods have been tried for counting the particles in a water droplet of the polystyrene aerosol. The criteria for a satisfactory method of counting particles are discussed. A proposed method to accomplish this is to use carbon-14 labeled polystyrene hydrosols. (For preceding period see ARF-3127-6.) (B.O.G.)

Tests were conducted on a laboratory and semi-plant scale to determine the effect of permitting scrap grossly contaminated with uranium to be used in steel manufacture. It was found the most of the uranium is removed with the slag. Steel made with this scrap would have a uranium constituent so little above that made with uncontaminated scrap as to be hardly significant. The slag itself would not present any hazard in handling or normal use. It is recommended, therefore, that in the future steel with only surface uranium contamination be released through normal scrap channels.