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논문 기본 정보
- 자료유형
- 학술대회자료
- 저자정보
- 발행연도
- 2015.11
- 수록면
- 3,887 - 3,890 (4page)
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이 논문의 연구 히스토리 (3)
2015
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After the Fukushima accidents, it has been one of the key issues to keep the integrity of the containment during a severe accident. In Korea, adding containment filtered venting system (CFVS) installed as one of the Fukushima actions to an existing nuclear power plant has been suggested as one approach to mitigate the effects of a severe accident such as Loss of Coolant Accident (LOCA), Steam Generator Tube Rupture (SGTR) and Station Blackout (SBO), etc. CFVS was first installed at Wolsong unit 1 which is the CANDU type reactor.
CFVS which does not require an external source of power is used to prevent loss of containment integrity as a result of over-pressurization and relieve containment pressure for the conditions that could be present in a severe accident, and provide reliable venting function for containment pressure control. CFVS is designed to open and to close isolation valves passively by an operator. CFVS is operated when the containment pressure exceeds the design pressure (225 ㎪(a)) and is closed when the containment pressure decreases below 150 ㎪(a) [1]. 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. That enables pressure to be reduced using a filtered system that retains and recirculates airborne radioactivity within containment and operates passively without the need for a power supply.
Compared with the pressurized water reactor (PWR) containment, the containment of CANDU reactor has lower resistance to internal pressure increase because they have no steel liner inside and design pressure itself is lower. In this regard, the analysis of the thermal-hydraulics behavior of CANDU reactor during a severe accident is needed to evaluate the containment integrity. Therefore, the aim of this study is to evaluate the depressurization performance of Wolsong unit1 considering CFVS operation during SBO using the MELCOR code developed at Sandia National Laboratories (SNL) for the U.S. Nuclear Regulatory Commission (NRC). In addition, in order to evaluate the effects of the CFVS performance, a sensitivity study depending on the different venting area of the CFVS was conducted. Finally, an analysis of the CFVS performance to evaluate the effects of filtering and scrubbing of radioactive material during a severe accident is important. The effects of filtration efficiencies for the filters of CFVS is evaluated and then a sensitivity study depending on decontamination factor (DF) of the filters was carried out.
CFVS which does not require an external source of power is used to prevent loss of containment integrity as a result of over-pressurization and relieve containment pressure for the conditions that could be present in a severe accident, and provide reliable venting function for containment pressure control. CFVS is designed to open and to close isolation valves passively by an operator. CFVS is operated when the containment pressure exceeds the design pressure (225 ㎪(a)) and is closed when the containment pressure decreases below 150 ㎪(a) [1]. 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. That enables pressure to be reduced using a filtered system that retains and recirculates airborne radioactivity within containment and operates passively without the need for a power supply.
Compared with the pressurized water reactor (PWR) containment, the containment of CANDU reactor has lower resistance to internal pressure increase because they have no steel liner inside and design pressure itself is lower. In this regard, the analysis of the thermal-hydraulics behavior of CANDU reactor during a severe accident is needed to evaluate the containment integrity. Therefore, the aim of this study is to evaluate the depressurization performance of Wolsong unit1 considering CFVS operation during SBO using the MELCOR code developed at Sandia National Laboratories (SNL) for the U.S. Nuclear Regulatory Commission (NRC). In addition, in order to evaluate the effects of the CFVS performance, a sensitivity study depending on the different venting area of the CFVS was conducted. Finally, an analysis of the CFVS performance to evaluate the effects of filtering and scrubbing of radioactive material during a severe accident is important. The effects of filtration efficiencies for the filters of CFVS is evaluated and then a sensitivity study depending on decontamination factor (DF) of the filters was carried out.
목차
Abstract
1. 서론
2. 모델링
3. 분석결과
4. 결론
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UCI(KEPA) : I410-ECN-0101-2016-550-002169520