Nuclear Engineering and Technology

Korean Nuclear Society (한국원자력학회)
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PARAMETRIC STUDIES ON THERMAL HYDRAULIC CHARACTERISTICS FOR TRANSIENT OPERATIONS OF AN INTEGRAL TYPE REACTOR

  • Choi, Ki-Yong (Thermal Hydraulic Safety Research Department Korea Atomic Energy Research Institute) ;
  • Park, Hyun-Sik (Thermal Hydraulic Safety Research Department Korea Atomic Energy Research Institute) ;
  • Cho, Seok (Thermal Hydraulic Safety Research Department Korea Atomic Energy Research Institute) ;
  • Yi, Sung-Jae (Thermal Hydraulic Safety Research Department Korea Atomic Energy Research Institute) ;
  • Park, Choon-Kyung (Thermal Hydraulic Safety Research Department Korea Atomic Energy Research Institute) ;
  • Song, Chul-Hwa (Thermal Hydraulic Safety Research Department Korea Atomic Energy Research Institute) ;
  • Chung, Moon-Ki (Thermal Hydraulic Safety Research Department Korea Atomic Energy Research Institute)
  • Published : 2006.02.01
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Abstract

Transient operations for an integral type reactor, SMART-P, have been experimentally investigated using a thermal-hydraulic integral test facility, VISTA (Experimental Verification by Integral Simulation of Transients and Accidents), in order to verify the system design and performance of the SMART-P, a pilot plant of SMART. The VISTA facility was subjected to various accident conditions such as feedwater increase and decrease, loss of coolant flow, and control rod withdrawal accidents in order to elucidate the thermal-hydraulic responses following such accidents and finally to verify the system design of the SMARTP. Full functional control logics have been implemented in the VISTA facility in order to control the required control action for an accident simulation. As one of the sensitivity tests to verify the PRHRS performance, the effects of the initial water level in the compensation tank are experimentally investigated. When the initial water level is 16%, the water is quickly drained and nitrogen gas is then introduced into the PRHR system, resulting in deterioration of the PRHRS performance. It is thus found that nitrogen ingression should be prevented to ensure stable PRHRS operation.

Keywords

References

  1. Chang, M. H. et al., 'SMART-An Advanced Small Integral PWR for Nuclear Desalination and Power Generation,' Proc. of Global 99, Jackson Hole, USA (1999)
  2. Chang, M. H. et al., 'Basic Design Report of SMART,' KAERI/TR-2142/2002 (2002)
  3. Kim, S. H. et al., 'Design Verification Program of SMART,' Proc. of GENES4/ANP2003, Kyoto, Japan, September 15-19 (2003)
  4. Choi, K. Y. et al., 'Dynamic System Characteristics Report of the High Temperature/High Pressure Thermal Hydraulic Test Facility (VISTA) for Power Variation,' KAERI/TR-2605/2003 (2003a)
  5. Choi, K. Y. et al., 'Characteristics and Performance Analysis of the Major Thermal Hydraulic Components in the High Temperature/High Pressure Thermal Hydraulic Test Facility (VISTA),' KAERI/TR-2606/2003 (2003b)
  6. Park, H. S. et al., 'Experiments for Heat Transfer Characteristics and Natural Circulation Performance of PRHRS of the High Temperature/High Pressure Thermal Hydraulic Test Facility (VISTA),' KAERI/TR-2656/2004 (2004a)
  7. Park, H. S. et al., 'Analysis Report of the Thermal Hydraulic Characteristics Report of the High Temperature/High Pressure Thermal Hydraulic Test Facility (VISTA) in Steady State Conditions,' KAERI/TR-2657/2004 (2004b)
  8. Choi, K. Y. et al., 'VISTA : Thermal-Hydraulic Integral Test Facility for the SMART Reactor,' The 10th Int. Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-10), Seoul, Korea, October 5-9 (2003c)
  9. Choi, K. Y. et al., 'Thermal-Hydraulic Characteristics during Transient Operation of the Integral Type Reactor,' The 4th Japan-Korea Symposium on Nuclear Thermal Hydraulics and Safety (NTHAS-4), Sapporo, Japan, November 28-December 1 (2004)
  10. Park, H. S. et al., 'Experiments on the Heat Transfer and Natural Circulation Characteristics of the Passive Residual Heat Removal System for the Advanced Integral Type Reactor,' Proc. of Int. Congress on Advances in Nuclear Power Plants (ICAPP '04), Pittsburgh, PA, USA, June 13-17 (2004c)
  11. Park, H. S. et al., 'Experimental and Analytical Studies on the Passive Residual Heat Removal System for the Advanced Integral Type Reactor,' The 6th Int. Conference on Nuclear Thermal Hydraulics, Operations and Safety (NUTHOS-6), Nara, Japan, October 4-8 (2004d)
  12. Chung Y. J. et al., 'Study on the Thermal Hydraulic Characteristics of a Residual Heat Removal System for the SMART Plant,' The 10th International Topical Meeting on Nuclear Reactor Thermal Hydraulics (NURETH-10), Seoul, Korea, October 5-9 (2003)