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2015
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After the Fukushima accidents, it has been one of the key issues to keep the integrity of the containment under a severe accident. In 2012, containment filtered venting system (CFVS) first installed at Wolsong unit 1 in Korea can be used to depressurizethe containment during a severe accident such as Station Blackout (SBO). In addition, the key function of CFVS is to reduce the radioactive material releasing from the containment to the environment through a high-efficiency scrubber and filters. CFVS is operated when the containment pressure exceeds the design pressure (124 kPa(g)) of the containment building, the operator opens CFVS isolation valves. Then steam and air in the containment flows out to the environment through the CFVS and the containment pressure decreases below 50 kPa(g).
The SBO accident is chosen to analyze the depressurization performance of Wolsong unit 1 in consideration of the CFVS operation. The thermal-hydraulic behavior in containment of Wolsong unit 1 was evaluated using the MELCOR code developed at Sandia National Laboratories (SNL) for the U.S. Nuclear Regulatory Commission (NRC). The geometry of Wolsong unit 1 was modeled with one cell divided into 4 control volumes such as containment, CFVS, CFVS building and environment, and the simulations were run up to 260,000 sec (72 hrs). Also, in order to carry out a sensitivity study, the flow path area as a variable parameter is chosen as 0.0065 ㎡, where this area indicates a venting size of the CFVS for 8 inch, 16 inch, 16 inch and 32 inch, respectively.
The results show that the containment pressure is repeatedly rising and falling but it decreases gradually after 46 hrs in case of operating CFVS. On the other hand, the pressure continuously increases and then exceeds the containment failure pressure (427 kPa(a)) at 45.7 hrs without operating CFVS. That is, the containment pressure is considerably decreased and the integrity of the containment could be maintained when CFVS was operated. Therefore, it seems that CFVS has the capacity to keep the containment pressure below the design pressure during SBO. In addition, there are large differences in the containment pressure depending on venting size of CFVS. We found that the decreasing rate of the pressure in the containment and water level in CFVS depends on the venting size of CFVS. In the future, analyses of aerosols, fission product, and radioactive material behavior in containment and remove performance of radionuclide in CFVS are planning to be conducted.
The SBO accident is chosen to analyze the depressurization performance of Wolsong unit 1 in consideration of the CFVS operation. The thermal-hydraulic behavior in containment of Wolsong unit 1 was evaluated using the MELCOR code developed at Sandia National Laboratories (SNL) for the U.S. Nuclear Regulatory Commission (NRC). The geometry of Wolsong unit 1 was modeled with one cell divided into 4 control volumes such as containment, CFVS, CFVS building and environment, and the simulations were run up to 260,000 sec (72 hrs). Also, in order to carry out a sensitivity study, the flow path area as a variable parameter is chosen as 0.0065 ㎡, where this area indicates a venting size of the CFVS for 8 inch, 16 inch, 16 inch and 32 inch, respectively.
The results show that the containment pressure is repeatedly rising and falling but it decreases gradually after 46 hrs in case of operating CFVS. On the other hand, the pressure continuously increases and then exceeds the containment failure pressure (427 kPa(a)) at 45.7 hrs without operating CFVS. That is, the containment pressure is considerably decreased and the integrity of the containment could be maintained when CFVS was operated. Therefore, it seems that CFVS has the capacity to keep the containment pressure below the design pressure during SBO. In addition, there are large differences in the containment pressure depending on venting size of CFVS. We found that the decreasing rate of the pressure in the containment and water level in CFVS depends on the venting size of CFVS. In the future, analyses of aerosols, fission product, and radioactive material behavior in containment and remove performance of radionuclide in CFVS are planning to be conducted.
목차
Abstract
1. 서론
2. 모델링
3. 분석결과
4. 결론
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