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THE HIGH-TEMPERATURE CHEMISTRY OF FISSION-PRODUCT ELEMENTS. Summary Report, August 1, 1962-July 31, 1963

Description: The high-temperature chemistry of oxides of ruthenium, palladium, rhondium, and iridium and chlorides of iridium, osmium, rhodium, and ruthenium is discussed with respect to crystal structure, thermodynannic properties, vaporization, formation, and dissociation. (N.W.R.)
Date: September 1, 1963
Creator: Merten, U & Bell, W E
Partner: UNT Libraries Government Documents Department

High-Temperature Gas-Cooled Reactor Critical Experiment and Its Application

Description: Two types of critical experiments were conducted in support of the 40- Mw(e) Peach Bottom HTGR nucleardesign program. The first was the test-lattice experiment, where detailed measurements of reaction rates were examined in a lattice having a cold neutron spectrum characteristic of the HTGR. This program provided a method for checking the resonance integral of thorium, the Doppler coeificient of thorium, the detailed flux distribution in the lattice, and control-rod effectiveness within a cell. The second experiment was designed as a gross test of the calculational procedures and data. A small critical experiment having a clean geometry and a composition similar to that of the HTGR was constructed. This assembly had approximately one-sixth the volume of the HTGR core and was surrounded on all sides by a 2-ft graphite reflector. Owing to the small core size and the large reflector area, this experiment provided a severe test of the calculational methods. Experiments with this facility encompassed reactivity-coefficient measurements, neutron-flux distributions, effectiveness of groups of control rods, and a measurement of the overall temperature coefficient. (N.W.R.)
Date: August 1, 1963
Creator: Bardes, R. G.; Brown, J. R.; Drake, M. K.; Fischer, P. U.; Pound, D. C.; Sampson, J. B. et al.
Partner: UNT Libraries Government Documents Department

High-Temperature Vapor-Filled Thermionic Converter

Description: Progress Development of a high temperature, vaporfilled thermionic converter for application with a nuclear reactor for space-vehicle electrical power generation is reported. Problems associated with the design and opera tion of a thermionic converter employing a UC-ZrC emitter, a cesium plasma for space charge neutralization, and a high-temperature collector are described. Emitter fabrication techniques are also described. A test cell employing a cylindrical UC-ZrC emitter, which was pressure bonded to a tantalum sleeve, and a low- temperature copper collector, was fabricated and operated for 400 hours to provide experimental data. The emitter was operated at temperatures of the order of 2000 deg C while the collector temperature was maintained at 200 to 300 deg C. A conceptual design for a thermionic power reactor incorporating the thermionic converter under development is also studied. It was concluded that a thermionic fuel element would be about 20 inches long and 0.68 inch in diameter and would incorporate 1O thermionic cells. The load voltage per fuel element would be about 14.5 volts and two elements would be connected in parallel (electrically) to provide an output of 29 volts. The over-all design would provide an electrical power level of approximately one megawatt. (auth)
Date: February 15, 1962
Creator: Campbell, A. E.; Carpenter, F. D.; Dunlay, J. B. & Pidd, R. W.
Partner: UNT Libraries Government Documents Department

HIGH-TEMPERATURE VAPOR-FILLED THERMIONIC CONVERTER. Quarterly Technical Progress Report for the Period Ending July 31, 1963

Description: Efforts were directed to the evaluation of materials, fabrication, and testing problems associated with the operation of high-temperature vapor-filled thermionic converters employing uranium-zirconium carbide emitters of cylindrical geometry. To date five of these converters have operated 5300 hr. Cell H, which had two cesium vials, was placed in operation, while final assembly of Cell K was completed. Cell H output was 56 watts at an emitter temperature of 2380 deg K. The cesium temperature optimum for maximum power was 637 deg K. A collector temperature optimum was not obtained due to cooling limitations. (auth)
Date: August 26, 1963
Creator: Skoff, R.
Partner: UNT Libraries Government Documents Department