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Friday, August 7, 2020 | History

3 edition of Two-phase transport & reactor safety found in the catalog.

Two-phase transport & reactor safety

proceedings of the Two-Phase Flow and Heat Transfer Symposium-Workshop, held in Fort Lauderdale, Florida, on 18-20 October 1976, [and presented by the Clean Energy Research Institute, University of Miami, Coral Gables, Florida]

by Two-Phase Flow and Heat Transfer Symposium-Workshop Fort Lauderdale, Fla. 1976.

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  • 2 Currently reading

Published by Hemisphere Pub. Corp. in Washington .
Written in English

    Subjects:
  • Two-phase flow -- Congresses.,
  • Heat -- Transmission -- Congresses.,
  • Nuclear reactors -- Safety measures -- Congresses.

  • Edition Notes

    Includes bibliographical references and index.

    Statementedited by T.N. Veziroğlu, S. Kakaç ; [sponsored by the National Science Foundation, Washington, D.C., and the School of Continuing Studies, University of Miami].
    ContributionsVeziroglu, T. Nejat., Kakaç, S., University of Miami. Clean Energy Research Institute., National Science Foundation (U.S.), University of Miami. School of Continuing Studies.
    Classifications
    LC ClassificationsTA357 .T95 1976
    The Physical Object
    Pagination4 v. (xv, 1416 p.) :
    Number of Pages1416
    ID Numbers
    Open LibraryOL4546284M
    ISBN 100891160523
    LC Control Number77014094

      Reactor Safety Study: An Assessment of Accident Risks in U.S. Commercial Nuclear Power Plants [NUREG/ (WASH)]. Description. This publication is a revision of IAEA Safety Standards Series No. NS-R-1, Safety of Nuclear Power Plants: Design. It establishes requirements applicable to the design of nuclear power plants and elaborates on the safety objective, safety principles and concepts that provide the basis for deriving the safety requirements that must be met for the design of a nuclear .

    Book Description. Nuclear Thermal-Hydraulic Systems provides a comprehensive approach to nuclear reactor thermal-hydraulics, reflecting the latest technologies, reactor designs, and safety considerations. The text makes extensive use of color images, internet links, computer graphics, and other innovative techniques to explore nuclear power plant design and operation. Description. The aim of this publication is to provide technical guidelines and practical information to assist Member States, operating organizations and regulatory bodies, on the basis of international good practices, and to manage the interface between nuclear safety and security at research reactor facilities in an integrated and coordinated manner.

    Abstract. The contents of the book are presented under the following chapter headings: (1) nuclear power reactor characteristics, (2) safety assessment, (3) reactor kinetics, (4) reactivity feedback effects, (5) reactivity-induced accidents, (6) fuel element behavior, (7) coolant transients, (8) loss-of-coolant accidents, (9) accident containment, and (10) releases of radioactive . Switch Board: Toll free: | Local: | TDD: Office of Public Affairs: Note that NRC no longer publishes a telephone directory NUREG/BR The information it contained is at this site. For security reasons, the NRC does not publish staff e-mail addresses in this online directory. If you.


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Two-phase transport and reactor safety: proceedings of the Two-Phase Flow and Heat Transfer Symposium-Workshop, October, Fort Lauderdale, Florida, USA Author: T Nejat Veziroğlu ; S Kakaç. Two-phase transport & reactor safety: proceedings of the Two-Phase Flow and Heat Transfer Symposium-Workshop, held in Fort Lauderdale, Florida, on October[and presented by the Clean Energy Research Institute, University of Miami, Coral Gables, Florida].

Single-Phase, Two-Phase and Supercritical Natural Circulation Systems provides readers with a deep understanding of natural circulation book equips the reader with an understanding on how to detect unstable loops to ensure plant safety and reliability, calculate heat transport capabilities, and design effective natural circulation loops, stability maps and.

System Upgrade on Feb 12th During this period, E-commerce and registration of new users may not be available for up to 12 hours. For online purchase, please visit us again. Advances of Computational Fluid Dynamics in Nuclear Reactor Design and Safety Assessment presents the latest computational fluid dynamic technologies.

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Nuclear Reactor Design and Analysis. This note will focus on the basics of nuclear reactor design. Topics covered includes: Design, and Licensing, Reactors and Core Concepts, Heating, Fuel, and Fuel Element Analysis, Reactor Flow and Pump Sizing, Introductory Neutronics, Six Factor Formula, Neutron Transport, Neutron Kinetics, Power Conversion Systems, Nuclear Safety and Nuclear Safety.

Thermo-Fluid Dynamics of Two-Phase Flow, Second Edition focuses on the fundamental physics of two-phase flow. Nuclear reactor transient and accident analysis; Energy systems; Power generation systems; Chemical reactors and process systems; Space propulsion; Transport.

Transport processes in boiling and two-phase systems, including near-critical fluids: Authors: Hsu, Y.-Y.; Graham, R. nucleate boiling mechanism, film boiling, and the transition between nucleate and film boiling.

The characteristics of two-phase flow are also investigated, giving attention to two-phase flow parameters and equations, the. Abstract. Much effort has been devoted to numerical resolution of the hydrodynamics in multiphase stirred reactors. The Eulerian–Eulerian model (or multi-fluid model) is the dominant approach and has been coupled with different turbulence models (such as the k–ɛ model, Reynolds stress model, explicit algebraic stress model, and large eddy simulation) to aid the.

Two Phase Transport and Reactor Safety: ISBN () Hardcover, McGraw-Hill Education, Founded inhas become a leading book price comparison site. Topics covered includes: Design, and Licensing, Reactors and Core Concepts, Heating, Fuel, and Fuel Element Analysis, Reactor Flow and Pump Sizing, Introductory Neutronics, Six Factor Formula, Neutron Transport, Neutron Kinetics, Power Conversion Systems, Nuclear Safety and Nuclear Safety Analysis.

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This book focuses on the two-phase flow problems relevant in the automotive and power generation sectors. It includes fundamental studies on liquid–gas two-phase interactions, nucleate and film boiling, condensation, cavitation, suspension flows as well as the latest developments in the field of two-phase problems pertaining to power generation systems.

1 Reactor Engineering Division, Jožef Stefan Institute, Jam Ljubljana, Slovenia. 2 Helmholtz-Zentrum Dresden-Rossendorf, Institute of Fluid Dynamics, Bautzner LandstraßeDresden, Germany.

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Transport of Interfacial Area Concentration in Two-Phase Flow. By Isao Kataoka, Kenji Yoshida, Masanori Naitoh, Hidetoshi Okada and Tadashi Morii. Submitted: April 26th Reviewed: September 8th Published: February 10th DOI: /Cited by: 4.

Nuclear Thermal-Hydraulic Systems provides a comprehensive approach to nuclear reactor thermal-hydraulics, reflecting the latest technologies, reactor designs, and safety considerations.

The text makes extensive use of color images, internet links, computer graphics, and other innovative techniques to explore nuclear power plant design and : Robert E.

Masterson.The first part of the book covers basic reactor physics, including, but not limited to nuclear reaction data, neutron diffusion theory, reactor criticality and dynamics, neutron energy distribution, fuel burnup, reactor types and reactor safety.Nuclear Energy: An Introduction to the Concepts, Systems, and Applications of Nuclear Processes, Eighth Edition, provides essential information on basic nuclear physics, systems and the applications of nuclear comprehensively covers Basic Concepts, Radiation and Its Uses, and Nuclear Power, providing students with a broad view of nuclear energy and science .