Steam separator modeling for various nuclear reactor transients
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Steam separator modeling for various nuclear reactor transients

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Published by Division of Reactor Plant Systems, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission in Washington, DC .
Written in English


  • Steam-separators -- Simulation methods.,
  • Centrifuges -- Simulation methods.,
  • Transients (Dynamics),
  • Nuclear reactors -- Fluid dynamics.

Book details:

Edition Notes

Statementprepared by C.Y. Paik ... [et al.].
ContributionsPaik, C. Y., Massachusetts Institute of Technology., Electric Power Research Institute., U.S. Nuclear Regulatory Commission. Office of Nuclear Regulatory Research. Division of Reactor and Plant Systems.
The Physical Object
Paginationxiv, 210, [1] p. :
Number of Pages210
ID Numbers
Open LibraryOL17834830M

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Six transients were used as forcing functions to generate the response of the two steam generator parameters for each nodalization. Steam separator modeling for various nuclear reactor transients. In a pressurized water reactor steam generator, a moisture separator is used to separate steam and liquid and to insure that essentially dry. Part Two addresses the principles of thermodynamics and relevant target phenomena in nuclear systems. Next, the book focuses on nuclear thermal hydraulics modeling, covering the key areas of heat transfer and pressure drops, then moving on to an introduction to SYS TH and computational fluid dynamics codes. Introduction. The function of the steam generator (SG) in an indirect cycle nuclear power plant (NPP) is to generate steam from the nuclear heat produced by fission reactions in the core during operation at power, and to act as a heat sink to remove decay—heat from fission products during both normal reactor shut down and for a postaccident scenario in the event that reactor core Author: C.W. Turner, K. Khumsa-Ang. A boiling water reactor (BWR) uses demineralized water as a coolant and neutron is produced by nuclear fission in the reactor core, and this causes the cooling water to boil, producing steam. The steam is directly used to drive a turbine, after which it is cooled in a condenser and converted back to liquid water. This water is then returned to the reactor core, completing the loop.

Boron transient effects on the behavior of IRIS reactor using dynamic modeling Article in Progress in Nuclear Energy –52 · November with 66 Reads How we measure 'reads'. Jul 07,  · Dynamic modelling of nuclear steam generators T. W. KerlinPhD, E. M. KatzPhD, J. FreelsMS, and J. ThakkarMS Nuclear Engineering Department, The University of Tennessee I. Introduction II. Approach Used in Steam Generator Modeling III. U-Tube Recirculation Type Steam Generator Characteristics IV. transient analyses of a complete Boiling Water Reactor (BWR) system including Reactor Pressure Vessel (RPV), realistic simulation of plant transients difficult because the effects of BOP are not known a coefficient, boron transport, steam separator modeling, motor-generator set dynamics, control systems, BOP, and containment. In Author: Hsiang-Chou Cheng, U.S. Rohatgi. Selection of a steam generator pressure control program for a MWe pressurized heavy water reactor power plant through transient analysis and "improvement of the steam separator performance.

Investigation of reactor transients and power patterns of a heavy water-moderated, boiling heavy water-cooled reactor /, by C. Graves, C. Marotta, H. G. Elrod, L. Berkowitz, F.E. Beers, Nuclear Development Corporation of America, and U.S. Atomic Energy Commission (page images at . The Thermal-Hydraulics of a Boiling Water Nuclear Reactor Richard T., Jr. Lahey, F. J. Moody. Categories: Technique\\Water Other readers will always be interested in your opinion of the books you've read. Whether you've loved the book or not, if you give your honest and detailed thoughts then people will find new books that are right for. An Experimental Investigation of Steam Condensation in the Presence of Non-Condensable Gases for Nuclear Plant Containment Research on Modular Modeling Method of Reactor Coolant System Based on THEATRe. Bo Shi, Zhao Thermal hydraulics, Transients (Dynamics), Nuclear power stations, Steady state, Accidents, Neutrons, Safety. THERMAL-HYDRAULICS OF NUCLEAR REACTORS Papers Presented at The Second International Topical Meeting on Nuclear Reactor Thermal-Hydraulics Santa Barbara, California, USA January , Sponsored by the American Nuclear Society American Society of Mechanical Engineers American Institute of Chemical Engineers Edited by Mati Merilo.