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Improved Zirconium Alloys Quarterly Report: April - June 1961

Description: Quarterly report documenting progress on a project to determine an improved zirconium alloy for service in superheated water and steam. This report describes the results of approximately 75 compositions that were prepared prior, and presently are being arc-melted and fabricated into corrosion specimens, continuing the investigations of the effect of zirconium purity and heat treatment on corrosion and resistance.
Date: July 11, 1961
Creator: Weinstein, Daniel & Holtz, F. C.
Partner: UNT Libraries Government Documents Department
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Conceptual Design of an In-Pile Package Loop for Fast Reactor Fuel Testing

Description: Report issued by the APDA over a design study conducted on an "in-pile package loop for use as a reactor fuel test facility" (p. 5). The results are presented and discussed. This report includes tables, and illustrations.
Date: July 28, 1961
Creator: Blessing, W. G.; Balsbaugh, R. R.; Bloomfield, D. E.; Busch, J. S.; Hennig, R. J.; Jens, W. H. et al.
Partner: UNT Libraries Government Documents Department
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Progress Report Pebble Bed Reactor Program: June 1, 1959-October 31, 1960

Description: From abstract: This report describes analytical and development work in connection with the Pebble Bed Reactor concept. The principle involved in the reactor is the heating of graphite pebbles by the fission of contained uranium and transfer of the heat generated to helium which is circulated through the permeable bed.
Date: July 1961
Partner: UNT Libraries Government Documents Department
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The Relativistic Doppler Problem

Description: Several equations are derived which are useful in high-energy nuclear cascade calculations. Special attention is given to the motion of the nucleons in the nucleus which gives rise to the relativistic Doppler problem when a high-energy particle is Incident on the nucleus. The effects of the exclusion principle are Included in the derived equations.
Date: July 12, 1961
Creator: Zerby, C. D.; Curtis, R. B. & Bertini, Hugo W.
Partner: UNT Libraries Government Documents Department
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Progress Report on Brazing of Columbium

Description: The investigation of procedures and the development of alloys for brazing columbium are discussed. A survey of binary phase diagrams reveals that the most promising brazing alloy system for experimental investigation lay in the titanium- and zirconium-base alloys. The preliminary evaluation of a large number of refractory-metal brazing alloys indicated that one binary, nine ternary, and two quaternary compositions show considerable potential for high- temperature service. (auth)
Date: July 5, 1961
Creator: Fox, C. W.
Partner: UNT Libraries Government Documents Department
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Calculation of the"Negative Mass" Instability for DCX-1

Description: The threshold for an instability by which space charge accumulates in a ring of ions circulating in a magnetic field with negative radial gradient is calculated for DCX-1. With present low densities, the energy spread necessary to quench the instability, a dew tens of Kev, is of the order of the observed energy spread.
Date: July 3, 1961
Creator: Fowler, T. Kenneth
Partner: UNT Libraries Government Documents Department
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HRE-E Replacement Reactor Study No. 2

Description: The results of a second HRE-2 replacement reactor design study are reported in which the mechanical, hydrodynamic, and nuclear aspects are discussed in detail. The reactor design which evolved from this study has a 21-in. dia x 42-in. long cylindrical core (vol = 200 liters) partially reflected by a 4-in. thick beryllium reflector, surrounded by a thorium blanket, and enclosed in a 52.0-in. ID steel pressure vessel. By making the Zircaloy-2 core tank, beryllium reflector, and thoria blanket rem… more
Date: July 3, 1961
Creator: Chapman, R. H.
Partner: UNT Libraries Government Documents Department
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Xenon Chase and Samarium Burnup in the HFIR

Description: Further calculations have been made in connection with xenon and samarium transients in the HFIR, including associated variations in the power distribution. Of particular interest was the possibility of burning samarium out of a core that has been shutdown for a prolonged period of time after eleven or more days of operation at full power. The results indicate that such a core between the ages of 11 and 13 days old can complete the normal 15-day cycle after samarium burning times of zero to 50 … more
Date: July 21, 1961
Creator: Cheverton. R. D.
Partner: UNT Libraries Government Documents Department
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Power Trace Analysis Codes SNAVELY and FIP for the IBM-7090

Description: Two programs were prepared for the purpose of obtaining objective statistical information concerning the HRT power trace. The PIP code was used to obtain frequency distributions of power peaks. The SNAVELY program computed the reactivity additions necessary to account for the observed power fluctuations. Frequency distributions were calculated concerning the size and rate of these additions. The behavior of fluid recirculation rates, variation in which could lead to reactivity changes, was also… more
Date: July 31, 1961
Creator: Tobias, M. L.; Vondy, D. R.; Fowler, T. B. & Lietzke, M. P.
Partner: UNT Libraries Government Documents Department
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Fueling Cost Estimates for the "Burn-up and Discard" Fuel Cycle of CANDU-Type Natural-Uranium Dioxide Heavy Water Power Reactors

Description: Fuel cycle costs for the burn up and discard fuel cycle were estimated for CANDU type natural uranium dioxide heavy water pressure tube reactors using the ground rules of the Thermal Breeder Reactor Evaluation group at ORNL to compare with costs claimed by the Canadians who use slightly different cost accounting bases. The high capital cost disadvantage of this type of reactor is expected to be overcome by the attainment of low fuel cycle costs made possible by high burn ups of low priced natur… more
Date: July 19, 1961
Creator: Van Winkle, R.
Partner: UNT Libraries Government Documents Department
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Ring-Joint Spring-Clamp Disconnect

Description: The Molten Salt Reactor Program requires simple, leak-detectable, radiation-resistant joints. The extreme requirements call for pressures up to 250 psi and temperatures to 1200 deg F. Leak rate objectives for the mechanical joints are less than 1 x 10/sup -7/ atm. cc/sec (30 cc/year) as tested by a helium mass spectrometer. Two integral ring-joint spring-clamp flange sets were designed, built and tested for coupling 1/2 and 1 1/2-in. pipe, respectively. Final inner (system to buffer) seal leak … more
Date: July 14, 1961
Creator: Holz, P. P. (Peter P.)
Partner: UNT Libraries Government Documents Department
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After Shutdown Cooling Requirements in the HFIR

Description: In order to insure against damage to the reactor in the event of a power failure, it is recommended that emergency forced circulation be provided for a period of about one hour after shutdown. After about one day's decay time, natural circulation cooling on the outside surface of a single fuel annulus should provide sufficient cooling to prevent meltdown. Maximum possible heat up rates at shorter decay times are indicated.
Date: July 20, 1961
Creator: Winters, C. E.
Partner: UNT Libraries Government Documents Department
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Minutes of Third Meeting of Reactor Decontamination Information Exchange Group at ORNL, June 1-2, 1961

Description: The third semiannual meeting of the AEC-sponsored Reactor Decontamination Information Exchange Group was help at ORNL during June 1 and 2 1961. Nine reactor installations including Chalk River, were represented by personnel from their decontamination research teams. Although the meeting was a series of informal round-table discussion, with wide publication not contemplated, each member subsequently summarized the decontamination research at this installation during the last six month for public… more
Date: July 24, 1961
Creator: Meservey, A. B.
Partner: UNT Libraries Government Documents Department
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Health and Safety Laboratory Fallout Program Quarterly Summary Report: March 1, 1961 - June 1, 1961

Description: Report that summarizes multiple laboratories' reports on global fallout deposition. Reports include data on Strontium-90 deposition recorded by the Health and Safety Laboratory, data from other laboratories, related interpretive reports, and recent publications related to fallout.
Date: July 1, 1961
Creator: Hardy, Edward P., Jr.; Rivera, Joseph & Frankel, Robert
Partner: UNT Libraries Government Documents Department
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Inorganic Electrolytes in Anhydrous Acetonitrile

Description: "The properties of solutions of KI, AgNO/sub 3/, CoCl/sub 2/, and CoBr/ sub 2/ in anhydrous acetonitrile were studied by means of measurements of electric conductance, density, viscosity, and spectrophotometry. The data are examined in the light of theoretical concepts of electrolytes. The properties of acetonitrile as an ionizing solvent are discussed briefly, and a summary of existing information for inorganic salts in this solvent is presented."
Date: July 1961
Creator: Janz, George J. & Marcinkowsky, A E
Partner: UNT Libraries Government Documents Department
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PM-3A Nuclear Power Plant Program

Description: From summary: Progress report on the production of detailed piping and equipment installation drawings for the PM-3A nuclear power plant program. Attention has been paid to the procurement of those valves and specialty items associated with the piping system.
Date: July 21, 1961
Creator: Martin Company. Nuclear Division.
Partner: UNT Libraries Government Documents Department
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