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Effect of Heat Flux on the Corrosion of Aluminum by Water. Part Iii. Final Report on Tests Relative to the High-Flux Isotope Reactor

Description: The effect of very high heat fluxes on the corrosion of 1100 and 6061 aluminum alloys by water was investigated. The test conditions generally simulated those expected to exist during operation of the High-Flux lsotope Reactor. At heat fluxes between 1 and 2 x l0/sup 6/ Btu/hr-ft/sup 2/ and with coolant temperatures and velocities in the ranges of 13l to 250 deg F and 3l to 51 fps, respectively, a layer of boehmite ( alpha Al/sub 2/O/sub 3/- H/sub 2/0), which has low thermal conductivity, forme… more
Date: December 20, 1961
Creator: Griess, J. C.; Savage, H. C.; Rainwater, J. G.; Mauney, T. H. & English, J. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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THE HEAT CAPACITY OF BERYLLIUM CARBIDE POWDER IN STAINLESS STEEL CAPSULES AS A FUNCTION OF TEMPERATURE (400-1800 F)

Description: The mean heat capacity of a sample of powdered beryllium carbide, a possible moderator material for a nuclear reactor, was determined as a function of temperature. A thin-walled stainless steel capsule containing the material was heated in an electric furnace and dropped into a water calorimeter. The following linear equation for mean heat capacity over the temperature range 50 f C-T f C as a function of temperature, T, was derived from the data by the method of least squares: C/sub p/ = 0.299 … more
Date: April 20, 1949
Creator: Powers, H.; Kostigen, T. & Trice, J.B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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MTR Fast Neutron Flux Measurements for Cycle 146

Description: The fast neutron fluxes in selected positions of the MTR were measured for Cycle 146. The measurements were made at the beginning, throughout, and at the end of the cycle (564 Mwd). Vertical traverses for each position monitors are shown. (auth)
Date: March 20, 1962
Creator: Weber, L. D. & Hogg, C. H.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Materials testing using laser energy deposition

Description: A convenient method for determining the elastic constants of materials has been devised using the energy from a Q-switched neodymium-glass laser. Stress waves are induced in materials having circular rod or rectangular bar geometries by the absorption of energy from the laser. The wave transit times through the material are recorded with a piezoelectric transducer. Both dilatation and shear wave velocities are determined in a single test using an ultrasonic technique and these velocities are us… more
Date: December 20, 1977
Creator: Wilcox, W.W. & Calder, C.A.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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EFFECT OF UNBROKEN LIGAMENTS ON STRESS CORROSION CRACKING BEHAVIOR OF ALLOY 82H WELDS

Description: Previously reported stress corrosion cracking (SCC) rates for Alloy 82H gas-tungsten-arc welds tested in 360 C water showed tremendous variability. The excessive data scatter was attributed to the variations in microstructure, mechanical properties and residual stresses that are common in welds. In the current study, however, re-evaluation of the SCC data revealed that the large data scatter was an anomaly due to erroneous crack growth rates inferred from crack mouth opening displacement (CMOD)… more
Date: February 20, 2003
Creator: Mills, W.J. and Brown, C.M.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Modern solid state laser materials

Description: This document contains visual aids used in an invited talk entitled Modern Solid State Laser Materials, presented at the Conference on Lasers and Electro-Optics (CLEO) held in Anaheim, California, on June 20, 1984. Interest at LLNL in solid state lasers focuses on evaluating the potential of solid state laser media for high average power applications, including inertial fusion power production. This talk identifies the relevant bulk material parameters characterizing average power capacity and … more
Date: June 20, 1984
Creator: Krupke, W. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Neutronics analysis for HYLIFE-II

Description: A preliminary neutronics analysis of the HYLIFE-2 reactor concept gives a tritium breeding ratio of 1.17 and a system energy multiplication factor of 1.14. Modified SS-316 (in which Mn is substituted for Ni) is superior to Hastelloy X and Hastelloy N as a firstwall material considering He generation, dpa-limited lifetime, and shallow-burial index. Since Flibe is corrosive to Mn metals, however, a favorable first-wall material is yet to be decided on. Flibe impurities considered (e.g., inherent … more
Date: December 20, 1990
Creator: Tobin, M.T.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Advances in Tandem Mirror fusion power reactors

Description: The Tandem Mirror exhibits several distinctive features which make the reactor embodiment of the principle very attractive: Simple low-technology linear central cell; steady-state operation; high-..beta.. operation; no driven current or disruptions; divertorless operation; direction conversion of end-loss power; low-surface heat loads; and advanced fusion fuel capability. In this paper, we examine these features in connection with two tandem mirror reactor designs, MARS and MINIMARS, and severa… more
Date: May 20, 1986
Creator: Perkins, L. J. & Logan, B. G.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Equipment for inspection of austenitic stainless steel pipe welds

Description: A computer controlled ultrasonic scanning system and a data acquisition and analysis system have been developed to perform the inservice inspection of welds in stainless steel sodium piping in the Fast Flux Test Facility. The scanning equipment consists of a six axis motion mechanism and control system which allows full articulation of an ultrasonic transducer as it follows the circumferential pipe welds. The data acquisition and analysis system consists of high speed ultrasonic waveform digiti… more
Date: August 20, 1979
Creator: Boehmer, W.D. & Horn, J.E.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Infrared NDT methods applied to solar cell and panel characterization

Description: Infrared nondestructive testing (NDT) methods are described that have a good potential for providing valuable data concerning solar cell or panel characteristics without requiring contact with the photovoltaic device. Preliminary tests with cells and panels were conducted and the infrared NDT results are presented and discussed. (MHR)
Date: October 20, 1978
Creator: Green, D. R. & Olsen, L. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Beryllium pressure vessels for creep tests in magnetic fusion energy

Description: Beryllium has interesting applications in magnetic fusion experimental machines and future power-producing fusion reactors. Chief among the properties of beryllium that make these applications possible is its ability to act as a neutron multiplier, thereby increasing the tritium breeding ability of energy conversion blankets. Another property, the behavior of beryllium in a 14-MeV neutron environment, has not been fully investigated, nor has the creep behavior of beryllium been studied in an en… more
Date: July 20, 1990
Creator: Neef, W.S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Evaluation, design, development, and delivery of a 1200-kV prototype termination. Eighth technical progress report, September 1-November 30, 1980

Description: Tests are continuing on the shatter-resistant weathercase models and small samples. Extensive studies of composite materials has resulted in characterization of the epoxy weathercase materials mechanical properties over a wide range of temperatures and lifetime. Progress is reported on the design of the full scale prototype termination.
Date: February 20, 1981
Creator: Billings, J S; Meyer, J R & Kolano, F J
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Evaluation of materials exposed to high-velocity, high-salinity, highly mineralized geothermal brine

Description: Using surface traces, scanning electron microscopy, and light microscopy, Ti-, Co-, Ni-, and Fe-base alloys were evaluated for erosion and stress corrosion cracking (SCC) after exposure at about 104{sup 0}C to the nozzle exhaust from acidified geothermal brine. Examples of erosion, SCC, and corrosion are shown. Results are evaluated in terms of synergism between erosion, corrosion, and stress. Repassivation kinetics might play a key role in the formation and growth of erosion cavities. Of the m… more
Date: August 20, 1978
Creator: Goldberg, Alfred & Kershaw, Robert P.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Continuous cryopump for steady-state Mirror Fusion Reactors

Description: The characteristics of Mirror Fusion Reactors, i.e., steady state operation, a low neutral gas density and a large gas throughput require unique vacuum pumping capabilities. One approach that appears to meet these requirements is a liquid helium cooled cryopump system in which a fixed portion can be isolated and degassed while the remainder continues to pump. The time to degas a rotating, fixed portion of the pumping area and the ratio of that area to the total area fixes the gas inventory in t… more
Date: September 20, 1982
Creator: Batzer, T. H. & Call, W. R.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
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Operating limits Hanford Production Reactors. Revision 2

Description: This report is applicable to the eight operating production reactors, B, C, D, DR, F, H, KE, and KW. It covers the following: operating parameter limitations; reactivity limitations; control and safety systems; reactor fuel loading; coolant requirements with irradiated fuel in reactor; reactor confinement; test facilities; code compliance; safety instrumentation and set points; and control criteria. Also discussed are administrative procedures for process control, training, audits and inspectio… more
Date: May 20, 1963
Creator: Owsley, G. F.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Preliminary Study of the Pile Effluent Piping System

Description: In order to carry out the program of increased pile operating levels either tube outlet temperature or the water flows must be increased. This program proposes a considerable increase in both the pile effluent water flow and temperature. Consequently an investigation was started of problems that might be encountered in the pile effluent system. Later, a decision was made that the portion of this investigation dealing with the effects of increased water flow would be handled by the Pile Material… more
Date: October 20, 1953
Creator: Jones, S. S.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Production test IP-285-C and supplement a measurement of operating temperatures of uncooled thermal shield cooling tube. Final report

Description: The iron thermal shields of the Hanford reactors are cooled by means of water flow through thermal cooling tubes embedded in the shield blocks. The flow rate, temperature rise, and allowable pressure in the tubes and the conditions under which some of the tubes may be out of service are specified in the process standards. Shield heat formation and heat transfer calculations are necessarily based on broad assumptions and are therefore usually reliable only for order of magnitude and trend predic… more
Date: July 20, 1960
Creator: Smalley, W. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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100-C water plant

Description: System curves for each portion of the C Area Water Plant were obtained from referenced work and are presented in figures. Field test data, corroborating the calculated curves, are presented as singular points on the same graphs. Present maxima capacity of the C Area Filter Plant was 121,000 gpm with 118,000 gpm available for use as primary reactor coolant. Modifications to the filter effluent piping would increase this available flow to about 180,000 gpm. Of the 118,000 gpm available for C Reac… more
Date: February 20, 1961
Creator: Agar, J. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Hanford Works monthly report, May 1950

Description: This is a progress report of the production reactors on the Hanford Reservation for the month of May 1950. This report takes each division (e.g., manufacturing, medical, accounting, occupational safety, security, reactor operations, etc.) of the site and summarizes its accomplishments and employee relations for that month.
Date: June 20, 1950
Creator: Prout, G. R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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