The Safety Depressurization Vent System (SDVS) of APR 1400 prevents Reactor Coolant System (RCS) from over-pressurization by discharging high pressure and temperature coolant through the I-sparger into the IRWST during an accident. If IRWST water temperature rises locally, around the sparger, beyond 200 °F by the discharged coolant, unstable steam condensation may occur and cause large pressure load on the IRWST wall. To investigate whether this condition could be avoided along with the most severe accident, Total Loss of Feed Water (TLOFW) event and to find the local temperature location for the I-typed sparger in APR 1400, the flow and temperature distribution of water in the IRWST pool is calculated by using CFX 4.4 computational fluid dynamic code. According to the results, the IRWST water temperature does not exceeds temperature limit upto 15 seconds after the opening of POSRVs. The location of the local temperature is estimated as the location above and below of the sparger discharge head by examining the flow and temperature field.
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10th International Conference on Nuclear Engineering
April 14–18, 2002
Arlington, Virginia, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-3597-9
PROCEEDINGS PAPER
Numerical Study on the Local Temperature in IRWST Pool Available to Purchase
H. S. Kang,
H. S. Kang
Korea Atomic Energy Research Institute, Yusung, Korea
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Y. Y. Bae,
Y. Y. Bae
Korea Atomic Energy Research Institute, Yusung, Korea
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J. K. Park
J. K. Park
Korea Atomic Energy Research Institute, Yusung, Korea
Search for other works by this author on:
H. S. Kang
Korea Atomic Energy Research Institute, Yusung, Korea
Y. Y. Bae
Korea Atomic Energy Research Institute, Yusung, Korea
J. K. Park
Korea Atomic Energy Research Institute, Yusung, Korea
Paper No:
ICONE10-22331, pp. 505-515; 11 pages
Published Online:
March 4, 2009
Citation
Kang, HS, Bae, YY, & Park, JK. "Numerical Study on the Local Temperature in IRWST Pool." Proceedings of the 10th International Conference on Nuclear Engineering. 10th International Conference on Nuclear Engineering, Volume 3. Arlington, Virginia, USA. April 14–18, 2002. pp. 505-515. ASME. https://doi.org/10.1115/ICONE10-22331
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