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The Effect of Sodium Vapor Formation on the Operation of the Enrico Fermi Reactor : an Estimate

Description: This technical report presents the results of some simplified calculations concerning the two-phase flow of sodium in the Enrico Fermi reactor. The rather large value for the specific volume of sodium vapor coupled with the resistance of the top axial blanket sections resulted in large pressure drops for even small values (by weight) of net vapor. It is concluded that the formation of any sodium vapor in the Enrico Fermi reactor produces "boiling disease", i.e. triggers an unstable condition wh… more
Date: July 1957
Creator: Kroeger, H. R. & Stephenson, J. W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Sodium Boiling Calculations

Description: The equations are derived for making rough calculations of the pressure drop required to produce a given mass flow through a subassembly for a given heat generation for cases where the vapor volume fraction is 0.9 or less. The ratio of vapor velocity to liquid velocity is left as a parameter that is varied form unreasonably low to unreasonably high values.
Date: July 2, 1957
Creator: Nicholson, R. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Summary Report - APDA Activities

Description: "Continued negotiations with combustion engineering culminated in the signing of a contract for the detail design and fabrication of the reactor vessel and rotating shield plug and plug container."
Date: July 1957
Creator: Atomic Power Development Associates, Inc.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Quantization of Crystal Vibrations

Description: "Although the Born-von Karman treatment of the dynamics of crystal lattices is superior to that of Debye, the conABSTRACTS tinuum model of Debye is more amenable to computation; therefore the Debye treatment is used to obtain frequencies at a maximum energy. From the classic Hamiltonian of the solid, quantization is carried out by the Schroedinger method. The thermodynamic functions are obtained, and the mean square displacement is derived"
Date: July 26, 1957
Creator: DeMarcus, W. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Notes on the A-2-Compiler System

Description: "An account is given of an extensive study of the A-2 Compiler System for the Remington Rand Univac digital computer. In particular, the following topics are discussed: application and performance of subroutines, segmenting, and introduction of subroutines to the library."
Date: July 15, 1957
Creator: Lanza, G. &
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Quarterly Report of the Solution Corrosion Group for the Period Ending July 31, 1957

Description: The second all-titanium loop, 100A Loop N, was placed in operation during the past quarter and has operated satisfactorily for more than 400 hr with uranyl sulfate solution at 250°C and approximately 100 psi.. Loop I has been modified to provide better control of the oxygen concentration in the circulation solution in order to study the effect on corrosion of various oxygen concentrations under dynamic conditions. A fourth test of the mockup of Zircaloy-2 - stainless steel transition joint used… more
Date: July 31, 1957
Creator: Griess, J. C.; Savage, H. C.; English, J. L.; Greeley, R. S.; Ulrich, W. C.; Buxton, S. R. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Some Calculations of Diffusion Controlled Thermal Gradient Mass Transfer

Description: Calculations are presented of the amount of mass transfer to be expected in liquid alkali metal-Ni alloy systems for two assumed diffusion mechanisms. In one, the boundary layer is assumed saturated and the transfer rate is limited by the rate of diffusion of solute into the liquid. In the other, the mass transfer rate is assumed to be limited by the diffusion rate of a component of the solid alloy to the solid surface. It is concluded that a more general hypothesis is needed.
Date: July 22, 1957
Creator: Keyes, J. J., Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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HRT-CP: Results of Solids Dissolution Tests

Description: A dissolution cycle in the chemical plant consists of refluxing with 10.8 M H2SO4 for 4 hours followed by refluxing for a like period with 4 M acid. In each of 3 tests in which 370 gram batches of simulated corrosion product solids were subjected to two dissolution cycles using 820 excess acid more than 99.6 of the solid material was dissolved (based on the amount of undissolved material collected). In another test using one dissolution cycle and 820 excess acid 99.5 of the solids material was … more
Date: July 30, 1957
Creator: Albrecht, W. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Investigation of Effectiveness of HRT System for Venting Gas from Back of Fuel and Blanket Circulating Pumps

Description: In the HRT, gas which is trapped in the motor cavities of the fuel and blanket circulating pumps during filling operations and any gas which may migrate into the motor cavity during operation is to accumulate in enlarged chambers located in the pump purge lines immediately above the pumps. It has been observed in the past that any gas present in the back of a pump tends to form a vortex above the center of the rotating shaft end. Testing showed that gas in the circulating stream does migrate in… more
Date: July 29, 1957
Creator: Moyers, J. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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A Calculation of the Gamma-Ray Spectrum of the Bulk Shielding Reactor

Description: A calculation was performed to determine the high energy portion of the gamma-ray flux at the surface of the uranium-aluminum BSF reactor. The flux was considered to consist entirely of the un-collided flux plus the Compton scattered flux. The four sources of primary gamma rays included in the calculation were prompt fission gamma rays, capture gamma rays from aluminum, capture gamma rays from uranium, and fission-product decay gamma rays. These sources were divided into four energy groups. Alt… more
Date: July 31, 1957
Creator: deSaussure, Gerard
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Irradiation Experiment on Aluminum Fuel Plates Containing a 48 Wt % Uranium - 3 Wt % Silicon - 49 Wt % Aluminum Alloy with 20% Enrichment in the U-235 Isotope

Description: Description of a planned test to evaluate the behavior of aluminum fuel elements, containing a 48 wt % U - 3 wt % Si - 49 wt % Al alloy, in which the uranium is enriched in theU-235 isotope at the 20% level. This alloy greatly minimizes fabrication problems associated with the binary 48 wt % U-Al previously tested.
Date: July 17, 1957
Creator: Beaver, R. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Treatments for the HRT Closed Cooling Water and Cooling Water System

Description: Potassium chromate is recommended as the corrosion inhibitor for the HRT closed cooling water system. A combination of sodium chromate and sodium phosphate ( Betz dianodic treatment) is recommended for the HRT cooling tower water system corrosion inhibitor. Algae growth in the cooling tower may be controlled by the periodic addition of chlorinated phenols to the cooling tower water.
Date: July 20, 1957
Creator: McLain, Howard A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Possibility of Interconnecting the HRT Pressurizers with an Open Pipe

Description: Calculations show that the transfer of solids from the core to the blanket side of the HRT is improbable when the two pressurizers are connected with an open pipe. The calculations show that the transfer of uranium or other dissolved solids from the fuel system to the blanket is not probable. Therefore it is believed that the HRT could not be operated without the presence of rupture discs between the pressurizers.
Date: July 17, 1957
Creator: McLain, Howard A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Prediction of Creep Failures of Lead in Bending From Tensile Data

Description: The creep rupture rates of lead beams in bending tests have been predicted within a factor of 3 based on tensile creep data. All of the specimens lasted longer than predicted. The underestimates in failure times correspond to over estimates in the maximum fibre stresses by about ten percent. If the nominal stresses reported in the tensile data are corrected for the fact that the tests were conducted under constant load instead of constant stress, the failure times of the bend specimens appear t… more
Date: July 17, 1957
Creator: Platus, D. L. & Cotton, B. Y.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Preliminary Aqua-Regia Dissolution Studies

Description: Batch and continuous aqua-regia dissolution of 304 and 304-L stainless steels, and AFFR plate were studies. Dissolution techniques are described and preliminary results are presented. A short survey of the known chemistry of aqua-regia is also presented.
Date: July 10, 1957
Creator: Fritz, K. J.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Description of ORNL Pool Type Critical Facility

Description: The Pool Type Critical Facility (PTCF) is a low powered, highly enriched (90 to 95% U/sup 235/) ordinary light water cooled and moderated, beryllium oxide reflected assembly. It is generally similar to the present BSR at ORNL, the principal modification being that the grid plate is arranged to accommodate both ORR and BSR fuel elements. The PTCF is located in the northwest corner of the existing BSR pool. The 9 x 7 lattice provides 63 fuel, control rod, or reflector positions.
Date: July 16, 1957
Creator: Bates, A. E. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Economics and Hazard Potential of Waste Disposal

Description: The two most important considerations in the disposal of radioactive wastes are safety and economy. All other steps in the waste disposal complex must be tuned to accomplish these two goals. In general, the hazardous waste in the nuclear power complex affect the cost of the nuclear power reactor fuel cycle, the general environment since disposal must exclude radioactivity from the environment for over 500 years, the costs and/or methods of waste treatment including fission product utilization, … more
Date: July 8, 1957
Creator: Arnold. E. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Effect of Core Corrosion Sample Assembly on HRT Critical Concentration

Description: An estimate has been made of the critical fuel concentration in the HRT, taking into account the effect of the core corrosion sample assembly. The estimate is based on a number of previous calculations of critical concentration in an un-poisoned reactor and one calculation of critical concentration as a function of poison level. The makeup of the first core corrosion sample assembly was used in calculating equivalent neutron poisoning effects. Figure 1 shows the estimated critical concentration… more
Date: July 18, 1957
Creator: Haubenreich, Paul N.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Nuclear Computations for HRE-3 Design : Equilibrium Results

Description: Various nuclear characteristics of two-region spherical homogeneous reactors have been computed in order to provide information for the design of HRE-3. Equilibrium isotope concentrations were established using an ORACLE code, and a two-group model was used to obtain critical concentrations and flux distributions. Breeding ratio is plotted as a function of reactor size, blanket thorium concentration, and other design and operating parameters, and the time required for a demonstration breeding i… more
Date: July 10, 1957
Creator: Rosenthal, M. W. & Fowler, T. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Radiation Level in the Stator Region of the HRT Fuel Circulation Pump

Description: The gamma dose rate in the motor region of the HRT fuel circulation pump was measured with the pump scroll full of radioactive solution. Extrapolation of the data to the solution activity expected in the pump under normal operation gives a dose rate well below that which would result in excessive gas production in the stator can within the life of the pump. The above dose rate does not include the effects of fast neutrons from the fuel solution or of the general cell radiation level in the vici… more
Date: July 3, 1957
Creator: Engel, J. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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The Volatilization of Fission Products by Melting of Reactor Fuel Plates

Description: Experiments in the controlled melting of irradiated fuel specimens, particularly of the APPR, STR, and MTR types have confirmed that prolonged heating in air at temperatures in excess of the melting point results in the release of a large portion of the radioactivity. On the other hand, a moderate amount of heating in air or steam sufficient only to melt a specimen results mainly in the partial volatilization of the rare gases; the halogens, iodine and bromine; and the alkali metals, cesium and… more
Date: July 15, 1957
Creator: Parker, Geogre W. & Creek, George E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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