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Mild coal gasification: Product separation, pilot-unit support, twin screw heat transfer, and H sub 2 S evolution

Description: Our general objective is to further the development of efficient continuous mild coal gasification processes. Our efforts this year have been in four main areas. A new thrust has been to identify and develop efficient processes to separate the vapor product stream into particulate-free liquid and mist-free gas. We continued work aimed at predicting heat transfer rates (hence throughput) in externally-heated twin-screw pyrolyzers. We sought to provide technical support for the design, installati… more
Date: August 9, 1991
Creator: Camp, D. W.; Wallman, P. H. & Coburn, T. T.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Pulse*Star Inertial Confinement Fusion Reactor: heat transfer loop and balance of plant considerations

Description: A conceptual heat transfer loop and balance of plant design for the Pulse*Star Inertial Confinement Fusion Reactor has been investigated and results are presented. The Pulse*Star reaction vessel, a perforated steel bell jar approximately 11 m in diameter, is immersed in Li/sub 17/Pb/sub 83/ coolant which flows through the perforations and forms a 1.5 m thick plenum of droplets around an 8 m diameter inner chamber. The reactor and associated pumps, piping, and steam generators are contained with… more
Date: May 9, 1984
Creator: McDowell, M. W. & Murray, K. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Core Power and Decay Time Limits for a Disabled LOFT ECCS

Description: An analysis was done to determine at what LOFT total core power (nuclear plus decay power) the ECCS could be inoperable. The criteria used for the analysis was that the maximum fuel clad temperature should not exceed 1650/sup 0/F given a loss of coolant. Calculations for natural convection cooling of the fuel by air with an inlet temperature of 580/sup 0/F determined that the limiting core power is 25 kW (discounted by 15 percent to 20 percent for potential uncertainties). Shutdown times are li… more
Date: January 9, 1978
Creator: Atkinson, S. A.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Overview of an Urban Canopy Parameterization in COAMPS

Description: The Coupled Atmosphere/Ocean Mesoscale Prediction System (COAMPS) model (Hodur, 1997) was developed at the Naval Research Laboratory. COAMPS has been used at resolutions as small as 2 km to study the role of complex topography in generating mesoscale circulation (Doyle, 1997). The model has been adapted for use in the Atmospheric Science Division at LLNL for both research and operational use. The model is a fully, non-hydrostatic model with several options for turbulence parameterization, cloud… more
Date: February 9, 2006
Creator: Leach, M J & Chin, H S
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

LOFT center module radiation heat transfer for L2-3 and L2-4

Description: A simplified version of the MOXY/SCORE computer program is used to evaluate the potential influence of radiation heat transfer on the peak cladding temperature and the peak guide tube temperature during the higher power loss-of-coolant tests in LOFT. The results of this study indicate that radiation heat transfer influences peak cladding temperature and peak guide tube temperature by as much as -177 K and +285 K, respectively.
Date: July 9, 1979
Creator: Chang, S. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Introduction to Hydrodynamics

Description: Various aspects of hydrodynamics and elastic--plastic flow are introduced for the purpose of defining hydrodynamic terms and explaining what some of the important hydrodynamic concepts are. The first part covers hydrodynamic theory; and discussed fundamental hydrodynamic equations, discontinuities, and shock, detonation, and elastic--plastic waves. The second part deals with applications of hydrodynamic theory to material equations of state, spall, Taylor instabilities, and detonation pressure … more
Date: January 9, 1979
Creator: Wilkins, M. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Droplet phase characteristics in liquid-dominated steam--water nozzle flow

Description: An experimental study was undertaken to determine the droplet size distribution, the droplet spatial distribution and the mean droplet velocity in low-quality, steam-water flow from a rectangular cross-section, converging-diverging nozzle. A unique forward light scattering technique was developed for droplet size distribution measurements. Droplet spatial variations were investigated using light transmission measurements, and droplet velocities were measured with a laser-Doppler velocimeter (LD… more
Date: August 9, 1978
Creator: Alger, T.W.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Steam explosion analysis in support of the SRS reactor safety assessment

Description: This report describes the application of two steam explosion models in support of the Probabilistic Risk Assessment (PRA) for the Savannah River Reactors. Theoretical models are required to estimate steam explosion yields in terms of kinetic energy, pressure shock and steam generated by the event. These quantities are used in the PRA to determine fission product barrier integrity in the reactor confinement following a hypothetical steam explosion. The basic preconditions for a steam explosion a… more
Date: October 9, 1992
Creator: Vonderfecht, B.E. & Smith, D.C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Temperature Measurement in Operating Reactors: In-Reactor Temperature Measurement Associated With Fuel Element Testing

Description: The Fuel Development operation at Hanford uses a variety of in-reactor facilities to test experimental and prototypical fuel elements. High pressure-high temperature water loops in constant use are the 6 in. {times} 9 in. ETR core facility, the 3 in. {times} 3 in. ETR reflector facility and four front-to-rear loops in the 100-K East reactor at Hanford. Low pressure water cooled test facilities in use are located in the MTR the various Hanford reactors. Stainless steel sheathed the thermocouples… more
Date: December 9, 1959
Creator: Wheeler, R. G.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Conversion ratio consideration in the E-N fringe loading

Description: This document summarizes the requested study of theoretical factors influencing the expected conversion ratio of the fringe enrichment portion of an E-N loading. Exact calculation of the quantity is very complicated and will not be attempted here; however, it is possible, with simple geometric approximations, to derive relative conversion ratios. This present report summarizes the results of a study incorporating actual operating data from the present poisoned top and unpoisoned bottom fringe l… more
Date: January 9, 1961
Creator: Bowers, C. E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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Design criteria for coolant backup three remaining smaller reactors. Revision 1

Description: This document defines the objectives, bases, and functional requirements that shall govern the preparation of design of the coolant backup system for the three remaining smaller reactors. This project will increase the reliability of the coolant backup facility at B Area by providing an independent last-ditch coolant system to B and C Reactors. The reliability of the last-ditch system for D Reactor will also be improved in that the present F and H leg of the export system will no longer be a pa… more
Date: June 9, 1964
Creator: Brinkman, L. B.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Thermo-hydraulic analysis of superconducting toroidal-field magnets for the Tokamak Physics Experiment

Description: The superconducting magnets in Fusion Reactors are subjected to pulsed, nuclear, and resistive heating. The thermo-hydraulic response of the helium forced-flow cooled conductors to the various heat sources is critical to magnet design and performance. Recently developed computer codes allow accurate modeling of conductor response and have been used as an aid to design of the toroidal field (TF) magnets for the Tokamak Physics experiment (TPX). We present results of design studies that determine… more
Date: July 9, 1993
Creator: Wong, R. L.; Zbasnik, J. P. & Hassenzahl, W. V.
Item Type: Refine your search to only Article
Partner: UNT Libraries Government Documents Department
open access

Irradiation performance of enriched uranium clad in stainless steel: PT-IP-123-A. Final report

Description: Early in the development of an extended surface fuel element for use in the NPR, several 7-rod cluster fuel elements were irradiated to determine the dimensional stability of such geometries at high burnups. These elements were fabricated from small diameter uranium rods clad unbonded in stainless steel tubes and assembled in a rod cluster geometry by various support devices. Zircaloy clad fuel rods were not yet available, the stainless steel clad rods therefore served as a suitable material wh… more
Date: June 9, 1959
Creator: Claudson, T. T.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Microtube strip heat exchanger. Final technical report

Description: The purpose of this contract has been to explore the limits of miniaturization of heat exchangers with the goals of (1) improving the theoretical understanding of laminar heat exchangers, (2) evaluating various manufacturing difficulties, and (3) identifying major applications for the technology. A low-cost, ultra-compact heat exchanger could have an enormous impact on industry in the areas of cryocoolers and energy conversion. Compact cryocoolers based on the reverse Brayton cycle (RBC) would … more
Date: July 9, 1992
Creator: Doty, F. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Steam explosion analysis in support of the SRS reactor safety assessment

Description: This report describes the application of two steam explosion models in support of the Probabilistic Risk Assessment (PRA) for the Savannah River Reactors. Theoretical models are required to estimate steam explosion yields in terms of kinetic energy, pressure shock and steam generated by the event. These quantities are used in the PRA to determine fission product barrier integrity in the reactor confinement following a hypothetical steam explosion. The basic preconditions for a steam explosion a… more
Date: October 9, 1992
Creator: Vonderfecht, B. E. & Smith, D. C.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Engineering study of tank leaks related to hydraulic retrieval of sludge from tank 241-C-106. Revision 1

Description: This study evaluates hydraulic retrieval (sluicing) of the waste in single-shell tank 241-C-106 with respect to the likelihood of tank leaks, gross volumes of potential leaks, and their consequences. A description of hydraulic retrieval is developed to establish a baseline for the study. Leak models are developed based on postulated leak mechanisms to estimate the amount of waste that could potentially leak while sluicing. Transport models describe the movement of the waste constituents in the … more
Date: June 9, 1993
Creator: Lowe, S. S.; Carlos, W. C.; Irwin, J. J.; Khaleel, R.; Kline, N. W.; Ludowise, J. D. et al.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Microtube strip heat exchanger

Description: The purpose of this contract has been to explore the limits of miniaturization of heat exchangers with the goals of (1) improving the theoretical understanding of laminar heat exchangers, (2) evaluating various manufacturing difficulties, and (3) identifying major applications for the technology. A low-cost, ultra-compact heat exchanger could have an enormous impact on industry in the areas of cryocoolers and energy conversion. Compact cryocoolers based on the reverse Brayton cycle (RBC) would … more
Date: July 9, 1992
Creator: Doty, F. D.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Application of Stochastic Radiative Transfer Theory to the ARM Cloud-Radiative Parameterization Problem

Description: This project had two primary goals: (1) development of stochastic radiative transfer as a parameterization that could be employed in an AGCM environment, and (2) exploration of the stochastic approach as a means for representing shortwave radiative transfer through mixed-phase layer clouds. To achieve these goals, climatology of cloud properties was developed at the ARM CART sites, an analysis of the performance of the stochastic approach was performed, a simple stochastic cloud-radiation param… more
Date: April 9, 2012
Creator: Veron, Dana E.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Revision to technical criteria and bases pressurized, water cooled, graphite moderated production reactor

Description: Attached is a draft of revisions being made to subject document, HW-53612. These revisions pertain to the moderators only, and will be incorporated in an overall revision of the technical criteria, which will be issued soon. Requirements, criterion, and data are included.
Date: October 9, 1958
Creator: Dickeman, R. L.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Process tube expansion: 105-C conversion to self-supported fuel elements

Description: A method of reducing gas leakage and rear fate maintenance is to fix the rear gunbarrel and process tube to the shield and eliminate the need for a rear expansion bellows. This arrangement is being considered as part of the C-reactor conversion to self-supported fuel element program. The fixed rear gunbarrel will require that all hydraulic load and thermal expansion elongation of the tube be taken through the front bellows. In the event that tubes freeze in their channels, forces due to thermal… more
Date: August 9, 1961
Creator: Mollerus, F. J. Jr.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

Chemical, physical and reactivity changes in a full reactor E-N meltdown

Description: This report discusses the events from a chemical standpoint following a total loss of coolant disaster will not be altered in the melting reactor by the introduction of N metal. The interdiffusion of uranium and aluminum will be the dominating reaction, causing the blockage and tying up of the lithium in UAl{sub 3} which does not melt until after the uranium does. Pressure from the swelling UAl{sub 3} will extrude uranium-aluminum and lithium into graphite weep holes and block interfaces. The m… more
Date: February 9, 1959
Creator: Nilson, R.
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
open access

STOMP Subsurface Transport Over Multiple Phases, Version 4.0, User’s Guide

Description: This guide describes the general use, input file formatting, compilation and execution of the STOMP (Subsurface Transport Over Multiple Phases) simulator, a scientific tool for analyzing single and multiple phase subsurface flow and transport. A description of the simulator’s governing equations, constitutive functions and numerical solution algorithms are provided in a companion theory guide. In writing these guides for the STOMP simulator, the authors have assumed that the reader comprehends … more
Date: June 9, 2006
Creator: White, Mark D. & Oostrom, Martinus
Item Type: Refine your search to only Report
Partner: UNT Libraries Government Documents Department
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