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Title: Thermal-Hydraulic Mockup Tests with Two-Phase Thermosyphon for Cold Neutron Source

Abstract

The improvement and utilization promotion project of the Taiwan Research Reactor (TRR-II) is carrying out at the Institute of Nuclear Energy Research (INER). The Cold Neutron Source (CNS) with a two-phase thermosyphon will be installed in the heavy water reactor of TRR-II. The hydrogen cold loop of TRR-II CNS consists of a cylindrical moderator cell, a single transfer tube, and a condenser. The thermal-hydraulic characteristics of a two-phase thermosyphon are investigated against the variations of mass inventory, tube geometry and heat loads. The thermal-hydraulic experiments have been performed using a full-scale mockup loop and a Freon-11 as a working fluid. The scaling approach is that the mass-fluxes of the liquid and the vapor in the Wallis correlation are identical between hydrogen and Freon-11. So, the same density ratio and a scaling heat load are applied to the loop. The flooding limitations as a function of initial Freon-11 inventory, transfer tube diameter, transfer tube geometry, and heat loads are presented. (authors)

Authors:
; ; ;  [1];  [2]
  1. Institute of Nuclear Energy Research, P. O. Box 3-3, LungTan 32500, Taiwan (China)
  2. Gengood Engineering Corporation, No 36, Lane 362, Min-Sheng W. Road, Taipei, Taiwan 104 (China)
Publication Date:
Research Org.:
American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
OSTI Identifier:
21167805
Resource Type:
Conference
Resource Relation:
Conference: ICAPP'02: 2002 International congress on advances in nuclear power plants, Hollywood, FL (United States), 9-13 Jun 2002; Other Information: Country of input: France; 12 refs
Country of Publication:
United States
Language:
English
Subject:
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS; COLD NEUTRONS; CYLINDRICAL CONFIGURATION; DENSITY; GEOMETRY; HEATING LOAD; HEAVY WATER; HYDROGEN; INVENTORIES; MOCKUP; TAIWAN RESEARCH REACTOR; THERMAL HYDRAULICS; WORKING FLUIDS

Citation Formats

Lee, C H, Chan, Y K, Lee, D J, Chang, C J, and Hong, W T. Thermal-Hydraulic Mockup Tests with Two-Phase Thermosyphon for Cold Neutron Source. United States: N. p., 2002. Web.
Lee, C H, Chan, Y K, Lee, D J, Chang, C J, & Hong, W T. Thermal-Hydraulic Mockup Tests with Two-Phase Thermosyphon for Cold Neutron Source. United States.
Lee, C H, Chan, Y K, Lee, D J, Chang, C J, and Hong, W T. Mon . "Thermal-Hydraulic Mockup Tests with Two-Phase Thermosyphon for Cold Neutron Source". United States.
@article{osti_21167805,
title = {Thermal-Hydraulic Mockup Tests with Two-Phase Thermosyphon for Cold Neutron Source},
author = {Lee, C H and Chan, Y K and Lee, D J and Chang, C J and Hong, W T},
abstractNote = {The improvement and utilization promotion project of the Taiwan Research Reactor (TRR-II) is carrying out at the Institute of Nuclear Energy Research (INER). The Cold Neutron Source (CNS) with a two-phase thermosyphon will be installed in the heavy water reactor of TRR-II. The hydrogen cold loop of TRR-II CNS consists of a cylindrical moderator cell, a single transfer tube, and a condenser. The thermal-hydraulic characteristics of a two-phase thermosyphon are investigated against the variations of mass inventory, tube geometry and heat loads. The thermal-hydraulic experiments have been performed using a full-scale mockup loop and a Freon-11 as a working fluid. The scaling approach is that the mass-fluxes of the liquid and the vapor in the Wallis correlation are identical between hydrogen and Freon-11. So, the same density ratio and a scaling heat load are applied to the loop. The flooding limitations as a function of initial Freon-11 inventory, transfer tube diameter, transfer tube geometry, and heat loads are presented. (authors)},
doi = {},
url = {https://www.osti.gov/biblio/21167805}, journal = {},
number = ,
volume = ,
place = {United States},
year = {2002},
month = {7}
}

Conference:
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