DOI QR코드

DOI QR Code

THERMAL HYDRAULIC ISSUES OF CONTAINMENT FILTERED VENTING SYSTEM FOR A LONG OPERATING TIME

  • 투고 : 2014.03.19
  • 심사 : 2014.06.21
  • 발행 : 2014.12.25

초록

This study investigated the thermal hydraulic issues in the Containment Filtered Venting System (CFVS) for a long operating time using the MELCOR computer code. The modeling of the CFVS, including the models for pool scrubbing and the filter, was added to the input file for the OPR-1000, and a Station Blackout (SBO) was chosen as an accident scenario. Although depressurization in the containment building as a primary objective of the CFVS was successful, the decontamination feature by scrubbing and filtering in the CFVS for a long operating time could fail by the continuous evaporation of the scrubbing solution. After the operation of the CFVS, the atmosphere temperature in the CFVS became slightly above the water saturation temperature owing to the release of an amount of steam with high temperature from the containment building to the scrubbing solution. Reduced pipe diameters at the inlet and outlet of the CFVS vessel mitigated the evaporation of scrubbing water by controlling the amount of high-temperature steam and the water saturation temperature.

키워드

참고문헌

  1. A REVA's presentation to US Nuclear Regulatory Commission, "Filtered Containment Venting Systems: General Overview and Applicability to CANDU Plants," ML12206A266 (2012).
  2. S . W. CHO et al., "Regulatory Research of the PWR Severe Accident: Improvement of Severe Accident Analysis Method for KNSP," KINS/HR-464, Korea Institute of Nuclear Safety (2002).
  3. Y . S. NA et al., "The Effect of the Venting Area for CFVS on the Containment," Transactions of the Korean Nuclear Society Autumn Meeting, Korea (2013).
  4. Y . S. NA et al., "Design of Containment Filtered Venting System for Depressurization in Containment under Severe Accidents," Proceedings of ICAPP 2014, USA (2014).
  5. R . O. Gauntt et al., "MELCOR Computer Code Manuals Vol. 1: Primer and Users Guide Version 1.8.6 September 2005," SAND 2005-5713, Sandia National Laboratories (2005).
  6. R . O. Gauntt et al., "MELCOR Computer Code Manuals Vol. 2: Reference Manuals Version 1.8.6 September 2005," SAND 2005-5713, Sandia National Laboratories (2005).
  7. P . C. Owczarski and K. W. Burk, "SPARC-90: A Code for Calculating Fission Product Capture in Suppression Pools," Pacific Northwest Laboratory (1991).

피인용 문헌

  1. Application of ASTEC, MELCOR, and MAAP Computer Codes for Thermal Hydraulic Analysis of a PWR Containment Equipped with the PCFV and PAR Systems vol.2017, pp.1687-6083, 2017, https://doi.org/10.1155/2017/8431934
  2. Effectiveness and adverse effects of in-vessel retention strategies under a postulated SGTR accident of an OPR1000 pp.1881-1248, 2017, https://doi.org/10.1080/00223131.2016.1273145
  3. An Estimation of Volatile Iodine in a Pool at Low pH and High Iodide Concentrations Under Irradiation pp.1943-748X, 2019, https://doi.org/10.1080/00295639.2019.1574118