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A Low Cost Experimental Neutron Chain Reactor Part 2

Description: Description of cooling, shielding, controls are discussed for 100 kw and 1 Mw operation of a low cost experimental neutron chain reactor.
Date: February 5, 1954
Creator: Abernathy, Fred H.; Barrett, Lawrence G.; Berger, William A.; Dever, John A.; Maurer, John F.; Mesler, Russell B. et al.
Partner: UNT Libraries Government Documents Department
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Equilibrium Adsorption of Krypton and Xenon on Activated Carbon and Linde Molecular Sieves

Description: Equilibrium krypton and xenon adsorption isotherms were obtained for four varieties of charcoal and for Linde Molecular Sieves Types 4A and 5A, generally at 0, 25, and 60°c. Such data are of interest in connection with design and evaluation of adsorbers for radioactive noble gas fission products. The isotherms were fitted, by linear regression analysis, to straight-line forms of the Freundlich and Langmuir equations. The Freundlich linear equation gave the better fit and the parameters of this … more
Date: February 14, 1961
Creator: Ackley, R. D. & Browning, W. E., Jr.
Partner: UNT Libraries Government Documents Department
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Instrumentation Flow Plan Symbols and Recommended Drawings : a Standard System for ORNL Instrumentation Applications Work

Description: This report is presented in order to provide a satisfactory system of symbols and identifications for process-instrumentation equipment and to promote a uniformity of practice that will simplify and expedite instrumentation work. It is intended that the systems presented here should be capable of designating and identifying the multitude of instrumentation items which are used for control and operation of conventional processes, as well as for specialized work peculiar to ORNL. Instrument Socie… more
Date: February 21, 1958
Creator: Adams, R. K.; Davis, D. G. & Hyland, R. G.
Partner: UNT Libraries Government Documents Department
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The Nuclear Fuel Cycle: Prospects for Reducing Its Cost

Description: Nuclear fuel cost of 1.25 mills/kwh would make nuclear power competitive with conventional power in low-cost coal areas if capital and operating costs can be brought to within about 10 percent of those of coal-fired plants. Substantial decreases in fuel fabrication cost are anticipated by 1970; other costs in the fuel cycle are expected to remain about the same as at present. Unit costs and irradiation levels that would be needed to give a fuel cost of 1.25 mills/kwh are believed attainable by … more
Date: February 20, 1959
Creator: Albrecht, W. L.
Partner: UNT Libraries Government Documents Department
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Apparent Observations Ionic Sound Waves in an Arc Plasma

Description: Oscillations have been observed in a magnetically supported cylindrical rod of plasma. This rod of plasma can be the discharge occurring in the defining aperture of a Mode II, pressure gradient arc. Similar oscillations can also occur in the column of a Mode I arc. These oscillations appear to be the mechanism that drives the Mode II blowup phenomena.
Date: February 13, 1961
Creator: Alexeff, I. & Neidigh, R. V.
Partner: UNT Libraries Government Documents Department
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HRT Corrosion Samples -- Additional Data on Specimens Removed Prior to Run No. 20.

Description: Results of the examinations of corrosion specimens exposed in the HRT are presented. Specimens examined included (1) core screen samples, (2) core specimen array No. 1, (3) blanket specimen array No. 2, (4) core solution line specimen arrays No. 103 and 103A, (5) blanket solution line specimen array No. 203. Complete information is still not available on all the specimens removed from the reactor, however, those data which have been accumulated are presented. These include corrosion rates, com… more
Date: February 2, 1961
Creator: Baker, J. E.; Silverman, M. D.; Jenks, G. H. & Olsen, A. R.
Partner: UNT Libraries Government Documents Department
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Aircraft Nuclear Propulsion Project Quarterly Progress Report for Period Ending December 10, 1950

Description: Technical report detailing expansion of the Aircraft Nuclear Propulsion at the Oak Ridge National Laboratory. Major facilities completed at this time were the Shielding Rector, the ANP Critical Facility, and the 86-in. Cyclotron. Outlines further need for radiation damage studies. [From Summary]
Date: February 27, 1951
Creator: Briant, R. C.; Ellis, C. B. & Cottrell, W. B.
Partner: UNT Libraries Government Documents Department
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Homogeneous Reactor Project Progress Report: May-October 1959

Description: Report issued by the Oak Ridge National Laboratory discussing quarterly progress made by the Homogeneous Reactor Program. Descriptions of progress and studies conducted are presented. This report includes tables, illustrations, and photographs.
Date: February 10, 1960
Creator: Briggs, R. B.; Beall, S. E.; Lyon, R. N.; Bohlmann, E. G.; Ferguson, D. E.; McDuffie, H. F. et al.
Partner: UNT Libraries Government Documents Department
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Homogeneous Reactor Project Quarterly Progress Report: August-October 1956

Description: Report issued by the Oak Ridge National Laboratory discussing quarterly progress made by the Homogeneous Reactor Program. Descriptions of progress and studies conducted are presented. This report includes tables, illustrations, and photographs.
Date: February 19, 1957
Creator: Briggs, R. B.; Winters, C. E.; Beall, S. E.; Lane, J. A.; Bohlmann, E. G.; Bruce, F. R. et al.
Partner: UNT Libraries Government Documents Department
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Test of 6-in.-Thick Pressure Vessels. Series 3: Intermediate Test Vessell V-7A Under Sustained Loading

Description: Report describing tests conducted on a Heavy Section Steel Technology (HSST) vessel, V-7, that was repaired after being tested hydrostatically to leakage and was retested pneumatically as vessel V-7A. Pretest analyses and a complete set of test data are included, along with a description of the test vessel and a discussion of test facility design and performance
Date: February 1978
Creator: Bryan, R. H.; Cate, T. M.; Holz, P. P.; King, T. A.; Merkle, J. G.; Robinson, Godfrey C. et al.
Partner: UNT Libraries Government Documents Department
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Critical Concentrations for HRT-Type Reactors Subjected to Various Conditions

Description: Critical concentration calculations were made for several D2O-H2O moderated HRT-type reactors with 30- and 28-in. core diameters and pressure vessel diameters of 60 and 54 in. A core temperature of 300°C was assumed for all cases while the blanket temperatures assumed the values of 250, 280, and 300°C. The assumed moderator compositions were 80, 90, 100% D2O.
Date: February 6, 1959
Creator: Chalkey, Roger
Partner: UNT Libraries Government Documents Department
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Fuel-Cycle Analysis and Proposed Fuel and Burnable Poison Distribution and Loading for the HFIR and HFCE-2

Description: Further calculations have been made to determine the desired radial fuel distribution in the HFIR and in the forthcoming HFIR critical experiment. In the process the design of the core was changed to include a 1-cm-thick annular space of water between the two nearly equally thick fuel annuli, a metal-to-water ratio in the fuel annuli of 1.0 (0.050 in. thick plates and coolant channels ) was specified, and the active length of the core was increased from 18 to 20 in. Results of the calculations … more
Date: February 2, 1961
Creator: Cheverton, R. D.
Partner: UNT Libraries Government Documents Department
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Calculation of Wall-Scattered Gamma Radiation Escaping through a Shield Opening - Application to the HRT

Description: A simplified method was developed for calculating wall-scatter gamma radiation escaping through a shield opening. The method was applied to the HRT and the results showed that next to the line of sight contribution, scattering of the wall of the shield opening was the main contribution to the dose at the rear edge of the shield. Design charts were prepared that give the dose as a function of the gamma source location with the reactor cell.
Date: February 19, 1957
Creator: Claiborne, H. C. & Fowler, T. B.
Partner: UNT Libraries Government Documents Department
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Chemical Separation of Isotopes Section Semiannual Progress Report for Period Ending June 30, 1955

Description: The countercurrent gas-liquid system BF3(g)—anisole·BF3(l) for the concentration of boron isotopes has been studied. The single-storage separation factor varies from 1.039 at 0°C to 1.029 at 30°C. Rate of exchange is rapid, and, with efficient contacting equipment, complete exchange may be obtained in less than 15 sec. A total separation of 1.525 has been realized in laboratory equipment. The critical-product reflux reaction is quite efficient. Only about 55 moles of BF3 remain in each million … more
Date: February 23, 1956
Creator: Clewett, G. H. & Drury, J. S.
Partner: UNT Libraries Government Documents Department
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A Brief Review of thermal Gradient Mass Transfer in Sodium and NaK Systems

Description: The fact that material transport does occur under conditions of finite temperature difference in a flowing molten metal system was established. The rate mass transfer was thought to be either diffusion limited or solution rate limited. It is believed that the mass transfer of structural materials in Na or NaK systems is solution rate limited. The limiting process has not been qualitatively or quantitatively confirmed for the Inconel-Na or Inconel-NaK system. Increasing the maximum system wall t… more
Date: February 11, 1957
Creator: DeVan, J. H. & West, J. B.
Partner: UNT Libraries Government Documents Department
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The Corrosion of Various Stainless Steels in Synthetic Waste Solutions

Description: Technical report describing the tests on types 309, 316, and 347 stainless steel. These steels were tested for a total of 779 to 828 hours in three different synthetic waste solutions. Results shoe that the best all-around corrosion resistance to the test conditions was exhibited by 316 stainless steel, but in one solution 347 stainless steel was more resistant. [From Abstract]
Date: February 12, 1951
Creator: English, James L.
Partner: UNT Libraries Government Documents Department
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Effect of Pressure Differentials on Deflection of the Outer Fuel Plates of Brazed APPR Fuel Elements

Description: One of the considerations in designing a flat plate fuel element is the resistance of the fuel plates, especially the outer plates in the fuel plate array, to deflection and permanent deformation as a result of pressure differentials. An investigation was recently initiated wit the objective of obtaining preliminary information on the APPR-type fuel element to determine the effect of pressure differentials on the outer plates in the fuel assembly. The APPR-1 fuel element consists of 18 flat com… more
Date: February 7, 1957
Creator: Erwin, J. H. & Beaver, R. J.
Partner: UNT Libraries Government Documents Department
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Generalized Heat Conduction Code for the IBM-7090 Computer

Description: The IBM-70% code GHT has been programmed for the 7090computer, to be run under control of the IBM-7090 FORTAN Monitor System. By eliminating the use of tapes for intermediate number storage, it has been possible to reduce computing time by a factor of 26 over the 704. A minimum of three tapes are required; one for input, one for output, and the System tape. One scratch tape is required for transient problems, and one punch tape is required if the steady-state temperature distribution is to be p… more
Date: February 9, 1961
Creator: Fowler, T. B.
Partner: UNT Libraries Government Documents Department
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Boundary Conditions and Conservation Properties of FOPP, a Plasma Fokker- Planck Code

Description: The energy distribution of ions and electrons in DCX are being studied by means of the Fokker-Planck approximation to the Boltzmann equation. An IBM- 704 code, called FOPP, was constructed to solve simultaneously the coupled Fokker-Planck equations for each of the two species of particles. This report discusses the difference scheme employed and derives the boundary conditions necessary in order that this difference scheme conserve energy and particles in the absence of sources and sinks. In pa… more
Date: February 27, 1959
Creator: Fowler, T. Kenneth; Rankin, F. M. & Simon, A.
Partner: UNT Libraries Government Documents Department
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Metallurgy Division Quarterly Progress Report for Period Ending October 31, 1950

Description: Technical report outlining the rate of production of modified MTR type fuel elements for the Bulk Shielding Facility has proceeded. Includes compatibility test that were started as a guide in the selection of materials suitable for fuel-element fabrication. [From Summary]
Date: February 8, 1951
Creator: Frye, J. H.; Miller, E. C. & Bridges, W. H.
Partner: UNT Libraries Government Documents Department
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