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EXPERIMENTS ON THE PERFORMANCE SENSITIVITY OF THE PASSIVE RESIDUAL HEAT REMOVAL SYSTEM OF AN ADVANCED INTEGRAL TYPE REACTOR

  • Park, Hyun-Sik (Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute) ;
  • Choi, Ki-Yong (Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute) ;
  • Choi, Seok (Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute) ;
  • Yi, Sung-Jae (Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute) ;
  • Park, Choon-Kyung (Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute) ;
  • Chung, Moon-Ki (Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute)
  • Published : 2009.02.28

Abstract

A set of experiments has been conducted on the performance sensitivity of the passive residual heat removal system (PRHRS) for an advanced integral type reactor, SMART, by using a high temperature and high pressure thermal-hydraulic test facility, the VISTA facility. In this paper the effects of the opening delay of the PRHRS bypass valves and the closing delay of the secondary system isolation valves, and the initial water level and the initial pressure of the compensating tank (CT) are investigated. During the reference test a stable flow occurs in a natural circulation loop that is composed of a steam generator secondary side, a secondary system, and a PRHRS; this is ascertained by a repetition test. When the PRHRS bypass valves are operated 10 seconds later than the secondary system isolation valves, the primary system is not properly cooled. When the secondary system isolation valves are operated 10 or 30 seconds later than the PRHRS bypass valves, the primary system is effectively cooled but the inventory of the PRHRS CT is drained earlier. As the initial water level of the CT is lowered to 16% of the full water level, the water is quickly drained and then nitrogen gas is introduced into the PRHRS, resulting in the deterioration of the PRHRS performance. When the initial pressure of the PRHRS is at 0.1MPa, the natural circulation is not performed properly. When the initial pressures of the PRHRS are 2.5 or 3.5 MPa, they show better performance than did the reference test.

References

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Cited by

  1. Design of the VISTA-ITL Test Facility for an Integral Type Reactor of SMART and a Post-Test Simulation of a SBLOCA Test vol.2014, pp.1687-6083, 2014, https://doi.org/10.1155/2014/840109
  2. An integral effect test of a complete loss of reactor coolant system flow rate for the SMART design using the VISTA-ITL facility and its simulation with the MARS-KS code pp.1881-1248, 2017, https://doi.org/10.1080/00223131.2016.1273147