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Experimental study of DRACS thermal performance in a low-temperature test facility

  • Q. Lv
  • , H. C. Lin
  • , X. Sun
  • , R. N. Christensen
  • , T. E. Blue
  • , G. Yoder
  • , D. Wilson
  • , P. Sabharwall

Research output: Chapter in Book/Report/Conference proceedingConference contributionpeer-review

3 Scopus citations

Abstract

Direct Reactor Auxiliary Cooling System (DRACS) is a passive decay heat removal system proposed for the Fluoride-salt-cooled High-temperature Reactor (FHR) that combines coated particle fuel and a graphite moderator with a liquid fluoride salt as the coolant. The DRACS features three coupled natural circulation/convection loops, relying completely on buoyancy as the driving force. These loops are coupled through two heat exchangers, namely, the DRACS heat exchanger and the natural draft heat exchanger. To experimentally investigate the thermal performance of the DRACS, a scaled-down low- Temperature DRACS test facility (LTDF) has been constructed. The design of the LTDF is obtained through a detailed scaling analysis based on a 200-kW prototypic DRACS design developed at The Ohio State University. The LTDF has a nominal power capacity of 6 kW. It uses 1.0-MPa water as the primary coolant, 0.1-MPa water as the secondary coolant, and ambient air as the ultimate heat sink. Two accident scenarios simulated in the LTDF are discussed in this paper. In the first scenario, the DRACS startup scenario occurs with no initial flow in either the LTDF primary or secondary loop, and the system is launched from a cold state. In the second scenario, a reactor coolant pump trip process is studied, during which a flow reversal phenomenon in the DRACS primary loop occurs. In both scenarios, natural circulation flows are developed as the transients approach to their quasi steady states.

Original languageEnglish
Title of host publicationInternational Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015
PublisherAmerican Nuclear Society
Pages1645-1658
Number of pages14
ISBN (Electronic)9781510811843
StatePublished - 2015
Event16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015 - Chicago, United States
Duration: Aug 30 2015Sep 4 2015

Publication series

NameInternational Topical Meeting on Nuclear Reactor Thermal Hydraulics 2015, NURETH 2015
Volume2

Conference

Conference16th International Topical Meeting on Nuclear Reactor Thermal Hydraulics, NURETH 2015
Country/TerritoryUnited States
CityChicago
Period08/30/1509/4/15

Keywords

  • DRACS
  • Decay heat removal
  • FHR
  • Passive safety

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