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Assessment of research and development (R and D) needs in ammonia safety and environmental control

Description: This report characterizes the ammonia industry operations, reviews current knowledge of ammonia release and subsequent impacts, summarizes the status of release prevention and control methods and identify research and development needs for safety and environmental control. Appendices include: accidental spills and human exposure; adiabatic mixing of liquid nitrogen and air; fire and explosion hazards; and environmental impact rating tables. (PSB)
Date: September 1, 1981
Creator: Brenchley, D.L.; Athey, G.F. & Bomelburg, H.J.
Partner: UNT Libraries Government Documents Department
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Note on the cryostatic stability of superconducting composites

Description: A careful discussion is given of the ''equal area condition'' developed by Maddock et al. In order to make the essential points as clear as possible, analytical solutions are derived under simplifying assumptions (simple model for heat transfer by nucleate and film boiling liquid helium; constant heat conduction and specific heat) instead of using more realistic but less controllable computer calculations. A quantitative definition of the concept of a long wire is given. Num… more
Date: February 1, 1978
Creator: Gauster, W. F.
Partner: UNT Libraries Government Documents Department
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Status Report on the Argonne Advanced Research Reactor

Description: The interim design and development status is reported. The scope of the work was limited to conceptual design studies supported by critical experiments plus heat transfer and hydraulic tests. Design criteria, facility and site, reactor, core geometry and composition, fuel elements, reflector, core and reflector support structure, reactor vessel, control and instruments, primary coolant systems, secondary coolant system, auxiliary systems, experimental facilities, building layout and constructio… more
Date: November 1, 1961
Creator: Lennox, D. H.; Barts, E. W.; Batch, R. V.; Beyer, F. C.; Jorgensen, G. L.; Kelber, C. N. et al.
Partner: UNT Libraries Government Documents Department
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The Snap Ii Power Conversion System Topical Report No. 12. Boiler Development

Description: The SNAP II boilers which were designed are summarized. As shown by test results from the three boilers which were tested, a continuous progress in design was achieved. These designs were based on test data from both the SNAP I and SNAP II programs. As the quantity of data increased, physical models describing the heat transfer process were developed. These physical models provide the necessary correlation parameters which permit the extension of existing data to advanced design. Preliminary te… more
Date: July 17, 1961
Creator: Gido, R. G.; Koestel, A.; Haller, H. C.; Huber, D. D. & Deibel, D. L.
Partner: UNT Libraries Government Documents Department
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GAS-COOLED REACTOR PROGRAM QUARTERLY PROGRESS REPORT FOR PERIOD ENDING SEPTEMBER 30, 1961

Description: Progress is reported on investigations in support of the Experimental Gas-Cooled Reactor, the Pebble-Bed Reactor Experiment, Advanced reactor design and development, test facilities, components, and materials. Topics covered include EGCR physics, EGCR performance analyses, structural investigations, EGCR component and materials development and testing, EGCR experimental facilities, PBRE physics and design studies, fueled-graphite investigations, clad fuel development, design studies of advanced… more
Date: February 1, 1962
Partner: UNT Libraries Government Documents Department
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Severe accident core heatup transients in modular high temperature gas-cooled reactors without operating Reactor Cavity Cooling Systems

Description: The ultimate decay heat removal system for the current Modular High Temperature Gas-Cooled reactors is a completely passive natural convection air cooling loop. This paper considers an extremely remote accident scenario, where even this passive system fails, and heat rejection is only via a layer of thermal insulation to the reactor silo structure and the surrounding soil. The results show that even in this case the peak fuel temperatures remain well within safe limits. However, vessel and conc… more
Date: January 1, 1988
Creator: Kroeger, P. G.
Partner: UNT Libraries Government Documents Department
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Murgatroyd-an Ibm 7090 Program for the Analysis of the Kinetics of the Msre

Description: The IBM 7090 program Murgatroyd is a revised and extended version of the IBM 704 program PET-I, which solves (by a fifth-order Runge-Kutta procedure) the coupled firstorder differential equations for power, delayed neutron concentration, and temperature in a one-region reactor as a function of time, given an input reactivity variation represented by a series of linear ramps. The basic extensions were those which were necessary to include the effects of the separate heat capacities and temperatu… more
Date: April 1, 1962
Creator: Nestor, C. W. Jr.
Partner: UNT Libraries Government Documents Department
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First wall/blanket/shield design and optimization system

Description: First wall/blanket/shield design and optimization system (BSDOS) has been developed to provide a state-of-the-art design tool for fast accurate analysis. In addition, it has been designed to perform several other functions: (1) allowing comparison and evaluation studies for different concepts using the same data bases and ground rules, (2) permitting the use of any figure of merit in the evaluation studies, (3) optimizing the first wall/blanket/shield design parameters for any figure of merit u… more
Date: February 1, 1988
Creator: Gohar, Y.; Baker, C.; Attaya, H.; Cha, Y.; Majumdar, S. & Scandora, T.
Partner: UNT Libraries Government Documents Department
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Supporting Analysis for Thermal Suitability of Fuel Elements for SM-1A Core I Loading

Description: A recommended SM-1A Core I loading chart was derived from available, metallurgically acceptable elements at the SM-1A and SM-1 sites. The derivation was based on local thermal and hydraulic considerations of minimum elementto- element coolant channel clearances. These clearances were determined from field inspection measurements of outer fuel plate spacing, as modified by analytical calculations of plate ripple growth during exposure to reactor operating thermal stresses. (auth)
Date: January 10, 1962
Creator: Brondel, J. O.
Partner: UNT Libraries Government Documents Department
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Chemical Technology Division, Unit Operations Section Monthly Progress Report, June 1961

Description: An interfacial viseometer was built for use in an interfacial phenomena study. Installation of a 6-in.-ID foam separation column system was completed. The dispersiondrying-sintering characteristics of six low-nitrate batches of thoria sol material were studied. The average effective porosity of the CuO pellets used for reactor helium purification was determined to be 0.0545 for H/ sub 2/ transport and 0.0526 for CO transport. In continuous Zirflex dissolution studies, no H/sub 2/O/sub 2/ decomp… more
Date: January 23, 1962
Creator: Whatley, M. E.; Haas, P. A.; Horton, R. W.; Ryon, A. D.; Suddath, J. C. & Watson, C. D.
Partner: UNT Libraries Government Documents Department
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Organic Nuclear Reactors: An Evaluation of Current Development Programs

Description: Organic reactor technology is critically evaluated and areas of research and development work now lacking or inadequate for the successful development of this reactor concept are indicated. The development programs for present organic and heavy water moderated concepts appear generally adequate to reach specific goals. However, the narrow scope of the organic reactor program should be broadened to assure coverage of areas where the application of novel principles might result in marked economic… more
Date: May 1, 1961
Partner: UNT Libraries Government Documents Department
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Comprehensive energy-management program. Hybrid photovoltaic/thermal absorber. Annual report, September 1, 1980-December 31, 1981

Description: Research work was done during the reporting period on the two-part research program: (A) to improve energy conservation through increased unit and system efficiencies, energy management, and system optimization, and (B) to develop a novel, low-cost hybrid photovoltaic/thermal absorber. Performance tests were conducted on all the boilers and chillers on campus. Several corrective measures were indicated and implemented. A detailed survey of energy use by functions and consumption/demand study ha… more
Date: December 1, 1981
Creator: Kumar, G. N.; Sellers, J. P. & Dybczak, Z. W.
Partner: UNT Libraries Government Documents Department
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Development of a computer program for reactor core thermal hydraulics: finite differencing in a 3-D staggered mesh suitable for irregular boundary applications

Description: A formulation utilizing a finite difference scheme for the direct numerical simulation of time varying two-phase flow problems in three space dimensions with irregular boundary geometry is presented. The formulation of such problems introduces a complicated set of coupled non-linear partial differential equations for the conservation of mass, momentum, energy, appropriate constitutive equations, and equations of state coupling the two phases. Discretization of the partial differential equations… more
Date: unknown
Creator: Sha, W.T.
Partner: UNT Libraries Government Documents Department
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Final Report of Modeling of CWM Droplet Combustion

Description: The objective of the present study was to develop a one-dimensional, unsteady state model for coal-water mixture droplet combustion, and to compare the characteristic times for the various processes, such as water vaporization, devolatilization and char oxidation with available experimental data. A water film surrounding a spherical coal particle is considered to undergo vaporization by heat transfer from the hot air. After the water vaporization is complete, devolatilization begins. This proce… more
Date: October 1, 1983
Creator: Pandalai, Krish; Aggarwal, Suresh & Sirignano, William
Partner: UNT Libraries Government Documents Department
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SIMMER as a safety analysis tool

Description: SIMMER has been used for numerous applications in fast reactor safety, encompassing both accident and experiment analysis. Recent analyses of transition-phase behavior in potential core disruptive accidents have integrated SIMMER testing with the accident analysis. Results of both the accident analysis and the verification effort are presented as a comprehensive safety analysis program.
Date: January 1, 1982
Creator: Smith, L. L.; Bell, C. R.; Bohl, W. R.; Bott, T. F.; Dearing, J. F. & Luck, L. B.
Partner: UNT Libraries Government Documents Department
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SCORE-EVET: a computer code for the multidimensional transient thermal-hydraulic analysis of nuclear fuel rod arrays. [BWR; PWR]

Description: The SCORE-EVET code was developed to study multidimensional transient fluid flow in nuclear reactor fuel rod arrays. The conservation equations used were derived by volume averaging the transient compressible three-dimensional local continuum equations in Cartesian coordinates. No assumptions associated with subchannel flow have been incorporated into the derivation of the conservation equations. In addition to the three-dimensional fluid flow equations, the SCORE-EVET code ocntains: (a) a one-… more
Date: February 1, 1978
Creator: Benedetti, R. L.; Lords, L. V. & Kiser, D. M.
Partner: UNT Libraries Government Documents Department
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Optical properties of flyash

Description: The general aims of this research are to provide a fundamental scientific basis for the physical understanding and reliable calculation of heat transfer in coal combustion systems, particularly as it is influenced by the presence of inorganic constituents deriving from mineral matter in coal. (VC)
Date: April 1, 1992
Creator: Self, S.A.
Partner: UNT Libraries Government Documents Department
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Coolant mixing in LMFBR rod bundles and outlet plenum mixing transients. Progress report, December 1, 1979-February 29, 1980

Description: Information is presented concerning bundle geometry with wrapped and bare rods; LMFBR outlet plenum flow mixing; and theoretical determination of local temperature fields in LMFBR fuel rod bundles.
Date: January 1, 1980
Creator: Todreas, N.E.; Golay, M.W. & Wolf, L.
Partner: UNT Libraries Government Documents Department
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The collaborative program of research in engineering sciences

Description: Research programs in the following areas are briefly described: High-Temperature Gas-Particle Reactions; Mathematical Modelling of Plasma Systems; Metal Transfer in Gas Metal-Arc Welding; Multivariable Control of Gas Metal-Arc Welding; Synthesis of Heat and Work Integration Systems for Chemical Process Plants; Parity Simulation of Dynamic Processes; Fundamentals of Elastic-Plastic Fracture: Three-Dimensional and Mechanistic Modelling; and Comminution of Energy Materials. Publications from each … more
Date: August 1, 1989
Creator: White, D.C.
Partner: UNT Libraries Government Documents Department
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