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in subjects: "Liquid Flow"

open access

De-entrainment on vertical elements in air droplet cross flow. [PWR]

De-entrainment phenomena on vertical elements in air-water droplet cross flow are generated using a horizontal array of water spray nozzles and a draft-induced wind tunnel. These conditions are used to obtain experimental values of the de-entrainment efficiency of isolated elements (25.4-, 63.5-, and 101.6-mm-diam cylinders and a 76.2-mm-square tube), and of an array of 101.6-mm-diam cylinders. A flow model is developed that extrapolates the de-entrainment efficiency of isolated elements throug… more

Date: January 1, 1980

Creator: Dallman, J.C. & Kirchner, W.L.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Coolant mixing in LMFBR rod bundles and outlet plenum mixing transients. Progress report, December 1, 1979-February 29, 1980

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.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

A study of steady-state steam-water counterflow in porous media

Vapor-liquid counterflow in porous media arises in processes such as heat pipes, oil recovery and geothermal systems. Previous studies analysed these phenomena in separate contexts. This paper presents a unified description from which previous models result as limiting cases. The analysis includes capillarity, heat conduction, and Kelvin effects. The importance of each term to various processes is examined. Significantly, it is found that the critical heat flux is not constant but increases wit… more

Date: February 1, 1990

Creator: Satik, C.; Parlar, M. & Yortsos, Y.C.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

GCFR core thermal-hydralic design

The approach for developing the thermal-hydraulic core assembly designs for the gas-cooled fast reactor (GCFR) is reviewed, and key considerations for improving the core performance at all power and flow conditions are discussed. It is shown how the thermal-hydraulic core assembly designs evolve from evaluations of plant size, material limitations, safety criteria, and structural performance considerations.

Date: May 1, 1980

Creator: Schleuter, G.; Baxi, C.B. & Bennett, F.O.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Flashing inception in flowing liquids

The inception of net vaporization in flashing flows is examined. It is suggested that the flashing inception can be expressed as two additive effects. One is due to the static decompression which is a function of the initial temperature and also of the expansion rate. The other effect which is a function of Reynolds number and flashing index, is due to the turbulent fluctuations of the flowing liquid. It is shown that by taking a three standard deviation band on the turbulent velocity fluctuati… more

Date: April 1, 1980

Creator: Jones, O. C., Jr.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Results and predictions of scaled, nuclear large break loss-of-coolant experiments. [PWR]

Two 200% cold leg break loss-of-coolant experiments performed in the LOFT facility have exhibited early core-wide quenches which were not predicted by the RELAP4/MOD6 code. Posttest studies have shown that while the critical flow model used significantly affects the hydraulic calculation, the principal reason for not predicting the quench behavior lies in the area of post-CHF heat transfer. The ability of the code to calculate quenches using a modified heat transfer surface is demonstrated, the… more

Date: January 1, 1980

Creator: Grush, W. H.; Lin, J. C.; Linebarger, J. H. & Nelson, R. A. Jr.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Computational and experimental methods for enclosed natural convection

Two computational procedures and one optical experimental procedure for studying enclosed natural convection are described. The finite-difference and finite-element numerical methods are developed and several sample problems are solved. Results obtained from the two computational approaches are compared. A temperature-visualization scheme using laser holographic interferometry is described, and results from this experimental procedure are compared with results from both numerical methods.

Date: October 1, 1977

Creator: Larson, D.W.; Gartling, D.K. & Schimmel, W.P. Jr.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Growth of molten core debris pools in concrete. Part II. A. Pool growth in composite beds; B. Effect of overlaying steel layers. Final report, March 1, 1978-September 30, 1979. [LMFBR]

The heat and mass transfer processes taking place in molten core debris/concrete systems have been experimentally investigated. Two types of experiments have been conducted. The first experiment simulates the growth of a molten debris pool in a composite sacrificial bed. This experiment models debris pool growth in an inner, low-melting point, sacrificial material zone followed by a melting attack on the concrete bed. The purpose of the inner zone is to quickly melt and dilute the debris pool s… more

Date: December 26, 1979

Creator: Abdel-Khalik, S I

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

MININR: a geochemical computer program for inclusion in water flow models - an application study

MININR is a reduced form of the computer program MINTEQ which calculates equilibrium precipitation/dissolution of solid phases, aqueous speciation, adsorption, and gas phase equilibrium. The user-oriented features in MINTEQ were removed to reduce the size and increase the computational speed. MININR closely resembles the MINEQL computer program developed by Westall (1976). The main differences between MININR and MINEQL involve modifications to accept an initial starting mass of solid and necess… more

Date: February 1, 1984

Creator: Felmy, A. R.; Reisenauer, A. E.; Zachara, J. M. & Gee, G. W.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

OTEC cold water pipe design for problems caused by vortex-excited oscillations

Vortex-excited oscillations of marine structures result in reduced fatigue life, large hydrodynamic forces and induced stresses, and sometimes lead to structural damage and to diestructive failures. The cold water pipe of an OTEC plant is nominally a bluff, flexible cylinder with a large aspect ratio (L/D = length/diameter), and is likely to be susceptible to resonant vortex-excited oscillations. The objective of this report is to survey recent results pertaining to the vortex-excited oscillati… more

Date: March 14, 1980

Creator: Griffin, O. M.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Assessment of molten debris freezing in a severe RIA in-pile test. [PWR; BWR]

An understanding of the freezing of molten debris on cold core structures following a hypothetical core meltdown accident in a light water reactor (LWR) is of importance to reactor safety analysis. The purpose of the present investigation was to analyze the transient freezing of the molten debris produced in a severe reactivity initiated accident (RIA) scoping test, designated RIA-ST-4, which was performed in the Power Burst Facility and simulated a BWR control rod drop accident. In the RIA-ST-… more

Date: January 1, 1980

Creator: El-Genk, Mohamed S. & Moore, Richard L.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Dynamic boiling tests in a 19-pin simulated LMFBR fuel assembly

A series of quasi-steady state tests were made to study dynamic boiling and to determine a boiling region which would not lead to immediate dryout and pin failure in the Thermal-Hydraulic Out-of-Reactor Safety (THORS) Facility (previously the Fuel Failure Mockup), an engineering-scale sodium loop for testing simulated LMFBR fuel assemblies at normal and off-normal operating conditions. These tests were made on an assembly consisting of 19 electrically heated pins of the same configuration as FF… more

Date: January 1, 1977

Creator: Wantland, J. L.; Clapp, N. E.; Fontana, M. H.; Gnadt, P. A. & Hanus, N.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

(Study of flow properties of wet solids using laser induced photochemical anemometry)

Research continues on the flow properties of wet solids. During this period we have made: progress in the analysis of the accuracy of the technique, progress in firming the foundations of LIPA for Solid-Liquid Mixtures, progress in the construction of better prototype skimmers, continued progress in chemically manufacturing both more red europium imbedded CaF{sub 2} and Green liquid Flowlite, and progress in understanding the coupling of LIPA chemicals snd dynamic range and timing. (VC)

Date: February 23, 1992

Creator: Falco, B.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Liquid-metal MHD flow in a duct whose cross section changes from a rectangle to a trapezoid, with applications in fusion blanket designs

This paper treats the liquid-metal MHD flow in a semi-infinite rectangular duct and a semi-infinite trapezoidal duct, which are connected by a finite-length transition duct. There is a strong, transverse, uniform magnetic field. The walls parallel to the magnetic field (sides) remain parallel, while the walls intersecting the magnetic field are twisted in the transition duct to provide the change in cross sectional shape. The left side has a constant height, while the height of the right side i… more

Date: April 1, 1986

Creator: Walker, J.S.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Flow-induced vibration for light water reactors. Final progress report, July 1981-September 1981

Flow-Induced Vibration for Light Water Reactors (FIV for LWRs) is a program designed to improve the FIV performance of light water reactors through the development of design criteria, analytical models for predicting behavior of components, and general scaling laws to improve the accuracy of reduced-scale tests, and through the identification of high FIV risk areas. The program is managed by the General Electric Nuclear Power Systems Engineering Department and has three major contributors: Gene… more

Date: November 1, 1981

Creator: Torres, M.R.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Scale-model characterization of flow-induced vibrational response of FFTF reactor internals

Fast Test Reactor core internal and peripheral components were assessed for flow-induced vibrational characteristics under scaled and simulated prototype flow conditions in the Hydraulic Core Mockup as an integral part of the Fast Test Reactor Vibration Program. The Hydraulic Core Mockup was an 0.285 geometric scale model of the Fast Test Reactor internals designed to simulate prototype vibrational and hydraulic characteristics. Using water to simulate sodium coolant, vibrational characteristic… more

Date: October 1, 1980

Creator: Ryan, J. A. & Mahoney, J. J.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Threshold of cavitation in orifices

No Description Available.

Date: January 1, 1975

Creator: Harris, S. D.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Heating and cooling the Raft River geothermal transite pipe line

A preliminary transient heat transfer analysis to aid in defining operating limits for the 4000-foot-long transite pipe line at the Raft River geothermal test site was completed. The heat transfer problem was to determine the time required to cool down the line from a 285/sup 0/F operating temperature to 50/sup 0/F and the time to heat up the line from 50/sup 0/F to 285/sup 0/F such that the temperature differential across the pipe wall will not exceed 25/sup 0/F. The pipe and the surrounding s… more

Date: June 1, 1977

Creator: Shaffer, C.J.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Liquid-metal flow through a thin-walled elbow in a plane perpendicular to a uniform magnetic field

This paper presents analytical solutions for the liquid-metal flow through two straight pipes connected by a smooth elbow with the same inside radius. The pipes and the elbow lie in a plane which is perpendicular to a uniform, applied magnetic field. The strength of the magnetic field is assumed to be sufficiently strong that inertial and viscous effects are negligible. This assumption is appropriate for the liquid-lithium flow in the blanket of a magnetic confinement fusion reactor, such as a … more

Date: April 1, 1986

Creator: Walker, J.S.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Advanced two-phase flow instrumentation program. Quarterly progress report, January-March 1980

Work performed to develop reliable liquid level sensors for in-vessel use in pressurized water reactors is described. During this period, an improved heated thermocouple level sensor was fabricated and techniques for separating thermocouple output signals from superimposed ac voltages were developed. Experiments that were performed with a thermal-type level sensor in natural convection to saturated water and steam are described. Pressures in those tests ranged from 0.1 to 10 MPa (15 to 1500 psi… more

Date: September 1, 1980

Creator: Turnage, K. G.; Davis, C. E.; Anderson, R. L. & Miller, G. N.

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Statistical evaluation of the effects of fall and winter flows on the spring condition of rainbow and brown trout in the green river downstream of Flaming Gorge Dam.

Flaming Gorge Dam, a hydroelectric facility operated by the Bureau of Reclamation (Reclamation), is located on the Green River in Daggett County, northeastern Utah. In recent years, single peak releases each day or steady flows have been the operational pattern during the winter period. A double-peak pattern (two flow peaks each day) was implemented during the winter of 2006-2007 by Reclamation. Because there is no recent history of double-peaking at Flaming Gorge Dam, the potential effects of … more

Date: January 9, 2009

Creator: Magnusson, A. K.; LaGory, K. E.; Hayse, J. W. & Division, Environmental Science

Item Type: Report

Partner: UNT Libraries Government Documents Department

open access

Results of recent reactor-material tests on dispersal of oxide fuel from a disrupted core

The results of experimental investigations and related analyses are reported addressing the dispersal of molten oxide fuel from a disrupted core via various available pathways for the CRBR system. These investigations included the GAPFLOW tests in which pressure-driven and gravity drainage tests were performed using dispersal pathways mocking up the intersubassembly gaps, the CAMEL C6 and C7 tests in which molten fuel entered sodium-filled control assembly ducts under prototypic thermal-hydraul… more

Date: January 1, 1985

Creator: Spencer, B. W.; Wilson, R. J.; Vetter, D. L.; Erickson, E. G. & Dewey, G.

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Numerical simulation of two-dimensional single- and multiple-material flow fields

Over the last several years, Sandia National Laboratories has had an interest in developing capabilities to predict the flow fields around vehicles entering or exiting the water at a wide range of speeds. Such prediction schemes have numerous engineering applications in the design of weapon systems. For example, such a scheme could be used to predict the forces and moments experienced by an air-launched anti-submarine weapon on water-entry. Furthermore, a water-exit prediction capability could … more

Date: January 1, 1992

Creator: Lopez, A.R.; Baty, R.S. (Sandia National Labs., Albuquerque, NM (United States)) & Kashiwa, B.A. (Los Alamos National Lab., NM (United States))

Item Type: Article

Partner: UNT Libraries Government Documents Department

open access

Development and validation of GWHEAD, a three-dimensional groundwater head computer code

A computer code has been developed to solve the groundwater flow equation in three dimensions. The code has finite-difference approximations solved by the strongly implicit solution procedure. Input parameters to the code include hydraulic conductivity, specific storage, porosity, accretion (recharge), and initial hydralic head. These parameters may be input as varying spatially. The hydraulic conductivity may be input as isotropic or anisotropic. The boundaries either may permit flow across th… more

Date: March 1, 1980

Creator: Beckmeyer, R.R.; Root, R.W. & Routt, K.R.

Item Type: Report

Partner: UNT Libraries Government Documents Department