Current-voltage characteristics of a cesium-on-tantalum thermionic converter with a collector temperature comparable to that of the emitter were obtained for a variety of electrode temperatures and cesium vapor pressures. The results show that for emitter temperatures in excess of 2000 deg K, power outputs of a few watts per square centimeter can be obtained when the ratio of collector temperature to emitter temperature is as high as 0.75 to 0.80, which is the required range for best performance of a radiation-cooled Carnot engine, and that at temperature ratios above 0.80 the power output is insensitive to changes in electrode spacing for ratios of spacing to electron mean free path greater than 100 at a cesium vapor pressure of 5 torr. (auth)

= 9 6 < ? < 0 t and fabrication method on irradiation stability, thermal conductivity, and hot hardness of uranium carbide were determined. Hypostoichiometric and stoichiometric uranium carbides prepared by both powder metallurgy and skull casting and hyperstoichiometric cast carbide were tested. The preparation of 12% enriched uranium carbide specimens for irradiation testing was completed. Sintered specimens were 98% of theoretical density for hypostoichiometric uranium carbide and 92 to 93% of theoretical for stoichiometric uranium carbide. All cast specimens were above 98.7% of theoretical density. Five different specimens, 4.4 and 4.8 450 deg C in a 0.1 wt% carbon, cast material and sintered material, and 5.2 450 deg C in a 0.1 wt% carbon, cast uranium carbide, were canned separately in niobium-1 wt% Zr and inserted into each of three capsules. The fuel specimens in capsule UNC-1-2 were contained in a sodium bond. This capsule was removed after 15,000 MW-d/ton U burnup in the MTR. The specimens in capsule UNC-1-3 were canned using an interference fit between cladding and fuel. This capsule was removed from the MTR after 14,440 MW-d/ton U burnup. Fuel surface temperatures ran in the range of 650 to 870 un. Concent 85% C and center-line …

This report documents information acquired from the operation of the purex process during the year of 1963 at the Hanford Site. The report is broken down into sections containing data collected on two to four week intervals. The data included: Performance, flowsheets, feed preparation, solvent extraction, product treatment, solvent treatment, acid recovery, waste concentration, fission product recovery, and waste treatment and storage.

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ABS>A system was created for processing large volumes of data from Project ROVER tests at the Nevada Test Site. The data are compiled as analog, frequency modulated tape, which is translated in a Packard-Bell Tape-to-Tape converter into a binary coded decimal (BCD) IBM 7090 computer input tape. This input tape, tape A5, is processed on the 7090 by the RDH-D FORTRAN-II code and its 20 FAP and FORTRAN subroutines. Outputs from the 7090 run are tapes A3, which is a BCD tape used for listing on the IBM 1401 input-output computer, tape B5 which is a binary tape used as input to a Stromberg-Carlson 40/20 cathode ray tube (CRT) plotter, and tape B6 which is a binary tape used for permanent data storage and input to specialized subcodes. The information on tape B5 commands the 40/20 to write grids, data points, and other information on the face of a CRT; the information on the CRT is photographed on 35 mm film which is subsequently developed; full-size (10" x 10") plots are made from the 35 mm film on a Xerox 1824 printer. The 7090 processes a data channel in approximately 4 seconds plus 4 seconds per plot to be made …

The purpose of this January, 1963 report is to review existing Redox exhaust gas sampling equipment and to propose modifications and additions where appropriate. A study was conducted to determine what modifications, if any, should be made to the Redox exhaust gas sampling equipment to improve their present methods of monitoring for excessive amounts of fission product activity.

The spread of a beam of particles can be represented by an ellipse in phase space, which represents the spread of the beam in both angle and distance. It is shown that the changes in this ellipse can be followed simply by graphical means, as the beam passes through an optical system consisting of thick and thin lenses and drift spaces. Such calculations are of value when an injected beam must be matched to an accelerator, or when a beam of particles from an accelerator must be transported to an experiment or through an anaiyzing system. The graphical calculation is quicker than a computer calculation, and should be of sufficient accuracy in most cases. The graphical calcuiation gives insight into the changes necessary in a beam transport system to give it the desired properties. (auth)

The bremsstrahlung emitted by an electron scattered in a Coulomb field was first calculated by Bethe and Heitler. The total cross section for production of photons with wave number between k and k + dk by a nonrelativistic electron of kinetic energy {epsilon} is d{sigma}/dk dk = 16/3 Z{sup 2}r{sub 0}{sup 2} (e{sup 2}/hc) (mc{sup 2}/{epsilon})log ({radical} {epsilon}/hck + {radical} {epsilon}/hck -1) dk/k, where Ze is the charge of the (heavy) ion, and r{sub 0} is the classical electron radius. Bremsstrahlung in a plasma has been computed by a number of authors in the approximation of replacing the Coulomb field by a cut-off Coulomb or static Debye potential. It is the purpose of this communication to call attention to another important effect of the medium upon the rate of emission of bremsstrahlung. This may be described as a modification of the relation of the photon's energy to its wave number, due to the index of refraction of the medium. Equivalently, we note that one must include in the calculation of bremsstrahlung in a medium the photon-medium interactions which result in the 'clothing' of a 'bare' photon. The replacement of a particle by a quasiparticle has long been known to be …

This memorandum discusses TORY II-C reactor control and reactor kinetics during simplified boost trajectories. Reactor start-up, power excursions, and automated control systems are investigated.

This is the monthly report for the Hanford Laboratories Operation, December 1962. Metallurgy, reactor fuels, chemistry, dosimetry, separation processes, reactor technology, financial activities, visits, biology operation, physics and instrumentation research, and employee relations are discussed.

Research and development progress is reported on water-cooled reactors, liquid-metal-cooled reactors, general reactor technology, plutonium-recycle reactor program, advanced systems research and development, and nuclear safety. (M.C.G.)