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

Conference ·
OSTI ID:21167805
; ; ;  [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)

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)

Research Organization:
American Nuclear Society, 555 North Kensington Avenue, La Grange Park, IL 60526 (United States)
OSTI ID:
21167805
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

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