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EXPERIMENTAL SIMULATION OF A DIRECT VESSEL INJECTION LINE BREAK OF THE APR1400 WITH THE ATLAS

  • Choi, Ki-Yong (Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute) ;
  • Park, Hyun-Sik (Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute) ;
  • Cho, Seok (Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute) ;
  • Kang, Kyoung-Ho (Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute) ;
  • Choi, Nan-Hyun (Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute) ;
  • Kim, Dae-Hun (Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute) ;
  • Park, Choon-Kyung (Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute) ;
  • Kim, Yeon-Sik (Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute) ;
  • Baek, Won-Pil (Thermal Hydraulics Safety Research Division, Korea Atomic Energy Research Institute)
  • Published : 2009.06.30

Abstract

The first-ever integral effect test for simulating a guillotine break of a DVI (Direct Vessel Injection) line of the APR1400 was carried out with the ATLAS (Advanced Thermal-hydraulic Test Loop for Accident Simulation) from the same prototypic pressure and temperature conditions as those of the APR1400. The major thermal hydraulic behaviors during a DVI line break accident were identified and investigated experimentally. A method for estimating the break flow based on a balance between the change in RCS inventory and the injection flow is proposed to overcome a direct break low measurement deficiency. A post-test calculation was performed with a best-estimate safety analysis code MARS 3.1 to examine its prediction capability and to identify any code deficiencies for the thermal hydraulic phenomena occurring during the DVI line break accidents. On the whole, the prediction of the MARS code shows a good agreement with the measured data. However, the code predicted a higher core level than did the data just before a loop seal clearing occurs, leading to no increase in the peak cladding temperature. The code also produced a more rapid decrease in the downcomer water level than was predicted by the data. These observable disagreements are thought to be caused by uncertainties in predicting countercurrent flow or condensation phenomena in a downcomer region. The present integral effect test data will be used to support the present conservative safety analysis methodology and to develop a new best-estimate safety analysis methodology for DVI line break accidents of the APR1400.

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