• Nuclear Engineering and Technology
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• 제54권1호
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• pp.177-185
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• 2022

Hydrogen risk in the containment filtered venting system (CFVS) vessel was analyzed, considering operation pressure and modes with the effect of PAR and accident scenarios. The CFVS is to depressurize the containment by venting the containment atmosphere through the filtering system. The CFVS could be subject to hydrogen risk due to the change of atmospheric conditions while the containment atmosphere passes through the CFVS. It was found that hydrogen risk increased as the CFVS opening pressure was set higher because more combustible gases generated by Molten Core Concrete Interaction flowed into the CFVS. Hydrogen risk was independent of operation modes and found only at the early phase of venting both for continuous and cyclic operation modes. With PAR, hydrogen risk appeared only at the 0.9 MPa opening pressure for Station Black-Out accidents. Without PAR, however, hydrogen risk appeared even with the CFVS opening set-point of 0.5 MPa. In a slow accident like SBO, hydrogen risk was more threatening than a fast accident like Large Break Loss-of-Coolant Accident. Through this study, it is recommended to set the CFVS opening pressure lower than 0.9 MPa and to operate it in the cyclic mode to keep the CFVS available as long as possible.

• Nuclear Engineering and Technology
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• 제46권6호
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• pp.797-802
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• 2014

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.

• Nuclear Engineering and Technology
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• 제53권3호
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• pp.812-824
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• 2021

In order to reduce risks from the Steam Generator Tube Rupture (SGTR) accident and to meet safety targets, various measures have been analyzed to minimize the amount of fission product (FP) release. In this paper, we propose an introduction of a Containment Filtered Venting System (CFVS) connected to the steam generator secondary side, which can reduce the amount of FP release while minimizing adverse effects identified in the previous studies. In order to compare the effect of new equipment with the existing strategy, accident simulations using MELCOR were performed. As a result of simulations, it is confirmed that CFVS operation lowers FP release into the environment, and the release fractions are lower (minimum 0.6% of the initial inventory for Cs) than that of the strategy which intends to depressurize the primary system directly (minimum 15.2% for Cs). The sensitivity analyses identify that refill of the CFVS vessel is a dominant contributor reducing the amount of FP released. As the new strategy has the possibility of hydrogen combustion and detonation in CFVS, the installation of an igniter inside the CFVS vessel may be considered in reducing such hydrogen risk.

• Journal of Radiation Protection and Research
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• 제40권4호
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• pp.244-251
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• 2015

본 연구에서는 격납건물의 건전성을 유지시켜 원전 주변의 오염범위를 축소할 수 있는 격납건물 여과배기계통(containment filtered venting system, CFVS)에 초점을 맞추고, 동 설비의 설치 전 후의 피해규모를 분석하여 여과장치의 효용성을 분석하였다. 본 연구에 사용된 코드는 확률론적 영향평가 코드인 MACCS2 이며, 평가에 이용한 사고선원항은 신고리 원자력발전소 1&2 호기의 확률론적 안전성 평가 보고서의 결과를 활용하였다. 주어진 총 19 개의 사고선원항 중 선정된 3 개의 방출군에 대하여 CFVS 적용 전후의 주민이 받는 유효선량과 갑상선선량을 산출하였다. 선량평가 결과는 거리에 따른 선량으로 산출되었으며, IAEA 주민보호조치 권고 기준인 갑상선방호약품 복용 및 방호조치가 필요한 갑상선선량과 유효선량을 초과하는 거리를 기준으로 비교하였다. STC-3, STC-4, STC-6 의 거리에 따른 유효선량은 전 범위(0~35 km)에서 95~99 % 내외의 감소율을 확인할 수 있었으며, 갑상선 선량의 경우 약 96~98 % 내외의 수준으로 유효선량과는 선량감소에서의 비슷한 경향이 있음을 확인 하였다. CFVS 를 적용한 후 대피 및 소개가 취해지는 유효선량 기준값을 초과하는 거리는 모든 방출군에 대하여 평균 1 km 내외로 평가되었다. 특히 STC-4 의 경우 26 km 에서 1.2 km 로 유효 선량을 초과하는 범위가 타 방출군에 비하여 대폭 줄어든 것을 확인할 수 있었다. 갑상선선량 기준값 초과거리의 경우 CFVS 를 적용한 후의 피해범위는 2~3 km 수준으로 산출되었다. 또한 갑상선선량 평가결과는 유효선량의 경우와 같이 STC-4 에서의 피해범위가 대략 50 km 줄어들어 CFVS 적용으로 가장 큰 효과를 보았다.

• Composites Research
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• 제20권2호
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• pp.1-9
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• 2007

카본 에폭시로 제작된 복합재 압력용기의 노화 특성과 구조 사용 수명 평가를 위해 실내와 실외에서 10년과 15년간 자연노화 시켰다. 노화 특성의 통계적 분포를 구하기 위해 노화된 압력용기로부터 링 시편을 채취하여 수압 파괴 시험을 실시하였다. 그리고 섬유와 수지 계면의 노화 특성 확인을 위해 시험 파편 계면을 SEM을 이용하여 관찰하였다. 섬유 인장 파손 변형률의 와이블 파라미터 값 기준으로 실내에서 10년, 15년 노화되었을 경우 각각 19%와 23% 저하되었으나, 실내와 실외의 노화 특성 차이는 크지 않았다. 그러나 압력용기 외면에 적용한 표면 페인트는 노화 방지에 큰 효과를 나타내었다.

• Nuclear Engineering and Technology
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• 제45권5호
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• pp.597-604
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• 2013

Containment Filtered Vent Systems (CFVSs) have been mainly equipped in nuclear power plants in Europe and Canada for the controlled depressurization of the containment atmosphere under severe accident conditions. This is to keep the containment integrity against overpressure during the course of a severe accident, in which the radioactive gas-steam mixture from the containment is discharged into a system designed to remove the radionuclides. In Korea, a CFVS was first introduced in the Wolsong unit-1 nuclear power plant as a mitigation measure to deal with the threat of over pressurization, following post-Fukushima action items. In this paper, the overall features of a CFVS installation such as risk assessments, an evaluation of the performance requirements, and a determination of the optimal operating strategies are analyzed for the Wolsong unit 1 nuclear power plant using a severe accident analysis computer code, ISAAC.

• Nuclear Engineering and Technology
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• 제53권6호
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• pp.1756-1768
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• 2021

The containment filtered venting system (CFVS) filters the atmosphere of the containment building and discharges a part of it to the outside environment to prevent containment overpressure during severe accidents. The Korean CFVS has a tank that filters fission products from the containment atmosphere by pool scrubbing, which is the primary decontamination process; however, prediction of its performance has been done based on researches conducted under mild conditions than those of severe accidents. Bubble behavior in a pool is a key parameter of pool scrubbing. Therefore, the bubble behavior in the pool was analyzed under various injection flow rates observed at the venturi nozzles used in the Korean CFVS using a wire-mesh sensor. Based on the experimental results, void fraction model was modified using the existing correlation, and a new bubble size prediction model was developed. The modified void fraction model agreed well with the obtained experimental data. However, the newly developed bubble size prediction model showed different results to those established in previous studies because the venturi nozzle diameter considered in this study was larger than those in previous studies. Therefore, this is the first model that reflects actual design of a venturi scrubbing nozzle.

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2012년도 추계학술논문요약집
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• pp.457-458
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• 2012

• 한국방사성폐기물학회:학술대회논문집
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• 한국방사성폐기물학회 2012년도 춘계학술논문요약집
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• pp.347-348
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• 2012

• 한국반도체및디스플레이장비학회:학술대회논문집
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• 한국반도체및디스플레이장비학회 2003년도 춘계학술대회 발표 논문집
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• pp.51-54
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• 2003

반도체 산업의 발전에 따라 생산과정에서의 반도체 소자의 특성을 검사하고, 오류를 검출하는 작업을 효율성 있게 하여 생산성을 향상시키는 것이 더욱 중요시 되고 있다. 이러한 흐름에 맞추어 반도체 test장비에 VFCS(voltage forcing current sensing)와 CFVS(current forcing voltage sensing)를 test 할 수 있게 개발하였다.