• Nuclear Engineering and Technology
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• 제54권9호
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• pp.3310-3316
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• 2022

Owing to the rising concerns about the safety of nuclear power plants (NPP), it is essential to study the venturi scrubber in detail, which is a key component of the filtered containment venting system (FCVS). FCVS alleviates the pressurein containment byfiltering and venting out the contaminated air. Themain objective of this research was to perform a CFD investigation of different configurations of a circular, non-submerged, self-priming venturi scrubber to estimate and improve the performance in the removal of elemental iodine from the air. For benchmarking, a mass transfer model which is based on two-film theory was selected and validated by experimental data where an alkaline solution was considered as the scrubbing solution. This mass transfer model was modified and implemented on a unique formation of two self-priming venturi scrubbers in series. Euler-Euler method was used for two-phase modeling and the realizable K-ε model was used for capturing the turbulence. The obtained results showed a remarkable improvement in the removal of radioactive iodine from the air using a series combination of venturi scrubbers. The removal efficiency was improved at every single data point.

• 한국정보통신학회논문지
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• 제27권1호
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• pp.109-116
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• 2023

본 논문에서는 다중 리더 에이전트와 추종 에이전트들로 구성된 2차 다중 에이전트 시스템의 봉쇄제어 문제를 연구하였다. 봉쇄제어의 목표는 추종 에이전트들을 다중 리더 에이전트들에 의해 생성되는 convex hulll을 추종하도록 하는 데에 있다. 따라서 리더 에이전트들에 의해 전체 그룹을 제어함으로써 다중 에이전트 시스템의 군집 행동을 얻을 수 있다. 본 논문에서 리더 에이전트들은 일정한 속도로 움직이고 추종 개체들은 입력 포화가 존재하는 경우를 고려하였다. 또한 추종 에이전트들은 이웃한 에이전트들과 상태 정보를 교환할 수 있고, 이웃과의 상대 상태 정보만 이용 가능하다 가정하였다. 이러한 가정하에 움직이는 리더 에이전트들을 고려한 봉쇄제어 문제를 해결하기 위해 비례-적분 기반의 분산제어 알고리즘을 제안하였다. 또한, 라살레 불변의 법칙을 기반으로 추종 에이전트들의 리더 에이전트들에 의해 생성되는 convex hull로 수렴을 보장하는 제어 이득들에 대한 조건들을 조사하였고 시스템 파라미터의 정보만으로 설계할 수 있음을 보였다. 마지막으로 모의실험을 통한 이론적 결과를 검증하였다.

• 항공우주시스템공학회지
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• 제17권5호
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• pp.19-27
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• 2023

본 연구에서는 유한요소해석을 이용하여 터빈 케이스의 컨테인먼트 성능 평가를 수행하였다. 충격 하중을 받는 구조물의 경우 변형률 속도가 증가함에 따라 유동 응력이 증가하기 때문에 충격 거동을 해석하기 위해서는 변형률 속도가 필수적으로 고려되어야 한다. 본 연구에서는 3가지 재료 모델(Cowper-Symonds, Johnson-Cook, Modified Johnson-Cook)을 충격 해석에 적용하고자 하였다. 해석에 적용된 재료 모델을 검증하기 위해서 알루미늄 6061 평판에 대한 충격 시험을 진행하였다. 실험과 해석 결과를 비교, 분석한 결과 Modified Johnson-Cook 모델이 가장 적은 오차를 보였다. 끝으로 해당 재료 모델을 터빈 케이스의 컨테인먼트 성능 평가에 적용하여 블레이드의 초기 속도에 따른 관통 여부와 충돌 부위에서 발생한 응력과 변형률을 제시하였다.

• Nuclear Engineering and Technology
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• 제18권3호
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• pp.183-193
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• 1986

실제 발전소규모의 HDR 격납용기 실험에서 기존의 격납용기 해석모델에 많은 문제점들이 있다는 것이 밝혀졌는데, 그 중의 하나가 단기 (0∼2초) 압력 차이 계산이다. 격납용기의 각 구분방 사이의 압력차이는 질량 흐름율, 유체밀도, 마찰상실계수, 흐름면적비 등에 의존하는데, 각 요소가 압력 차이의 실험값과 계산값의 불일치에 어느 정도의 영향을 주는가는 정확하게 알려져 있지 않다 본 연구에서는 기존의 해석모델을 개선하기 위해 지금까지 상수로 간주되어 온 마찰상실계수를 압력과 압력차이 등의 함수로 제시되었다. COMPARE 코드로 수정된 모델을 사용하여 HDR 실험에 대한 압력과 압력차이가 계산되었는데 V.42 실험값에서는 측정치와 잘 맞고, V.43의 측정치 보다는 높게, V.44 실험값보다는 조금 낮은 결과를 보였다.

• 한국전산구조공학회논문집
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• 제20권3호
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• pp.353-364
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• 2007

이 논문에서는 원전 격납건물의 극한내압능력 및 파괴모드 평가를 위해 개발된 비선형 유한요소해석 프로그램 NUCAS 코드에 대하여 기술하였다. NUCAS는 미시적인 재료모델을 도입한 퇴화 쉘 요소와 탄소성 재료모델을 도입한 저차고체요소로 구성되어 있고, 퇴화 쉘 요소와 저차고체요소는 유한요소에서 발생할 수 있는 강성과대(overstiffness) 및 묶임현상(locking phenomenon)을 방지하기 위해서 각각 가변형도법(assumed strain method)과 개선된 가변형도법(enhanced assumed strain method)을 적용하였다. 개발된 NUCAS코드의 성능을 검증하기 위해서 다양한 철근콘크리트 구조물의 벤치마크 테스트를 수행하였고, 그 결과로부터 이 논문에서 개발한 유한요소해석 프로그램의 해석결과는 실험결과와 잘 일치하였다.

• Computers and Concrete
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• 제13권1호
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• pp.1-16
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• 2014

To evaluate the behavior of the advanced unbonded pre-stressed concrete containment vessel (UPCCV) for one typical China nuclear power plant under Japan's March 11 earthquake, five nonlinear time history analysis and a nonlinear static analysis of a 1:10 scale UPCCV structure have been carried out with MSC.MARC finite element program. Comparisons between the analytical and experimental results demonstrated that the developed finite element model can predict the earthquake behavior of the UPCCV with fair accuracy. The responses of the 1:10 scale UPCCV subjected to the 11 March 2011 Japan earthquakes recorded at the MYG003 station with the peak ground acceleration (PGA) of 781 gal and at the MYG013 station with the PGA of 982 gal were predicted by the dynamic analysis. Finally, a static analysis was performed to seek the ultimate load carrying capacity for the 1:10 scale UPCCV.

• 한국안전학회지
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• 제30권5호
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• pp.123-130
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• 2015

Wolsong Unit 2,3&4 has been performing a containment integrity test during power operation. This test could impact to the safe operation during test. If an accident occurs during pressure dropping phase, reactor trip can be delayed because of the increased pressure difference which causes a time delay to reach the trip set-point. On the contrary, if an accident occurs during pressure increasing phase, reactor trip could be accelerated because the pressure difference to the trip set-point decrease. Point Lepreau nuclear power plant, which installed GCLMS (Gross Containment Leakage Monitoring System) in 1990, has discontinued the test since 1992 due to these adverse effects. Therefore, we evaluated the risk to obviate the GCLMS test based on PWR's ILRT (Integrated Leak Rate Test) extension methodologies. The results demonstrate that risk increase rate is not high in case of performing only ILRT test at every 5 years instead of doing GCLMS test at every 1.5 years. In addition, the result shows that GCLMS test can be removed on a risk-informed perspective since risk increasement is in acceptable area of regulatory acceptance criteria.

• International Journal of Naval Architecture and Ocean Engineering
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• 제8권6호
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• pp.537-553
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• 2016

This paper addresses the safety of two-row tank design by performing the extensive sloshing model tests. Owing to the uncertainties entangled with the scale law transforming the measured impact pressure up to the full scale one, so called comparative approach was taken to derive the design sloshing load. The target design vessel was chosen as 230 K LNG-FPSO with tow-row tank arrangement and the reference vessel as 138 K conventional LNG carrier, which has past track record without any significant failure due to sloshing loads. Starting with the site-specific metocean data, ship motion analysis was carried out with 3D diffraction-radiation program, then the obtained ship motion data was used as 6DOF tank excitation for subsequent sloshing model test and analysis. The statistical analysis was carried out with obtained peak data and the long-term sloshing load was determined out of it. It was concluded that the normalized sloshing impact pressure on 230 K LNG-FPSO with two-row tank arrangement is higher than that of convectional LNG carrier, hence requires the use of reinforced cargo containment system for the sake of failure-free operation without filling limitation.

• 한국지진공학회논문집
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• 제19권5호
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• pp.207-217
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• 2015

In order to increase seismic performance of nuclear power plant (NPP) in strong seismic zone, lead-rubber bearing (LRB) can be applied to seismic isolation system of NPP structures. Simple equivalent linear model as structural analysis model of LRB is more widely used in initial design process of LRB than a bilinear model. Seismic responses for seismically isolated NPP containment structures subjected to earthquakes categorized into 5 different soil-site classes are calculated by both of the equivalent linear- and bilinear- LRB models and compared each others. It can be observed that the maximum displacements of LRB and shear forces of containment in the case of the equivalent linear LRB model are larger than those in the case of bilinear LRB model. From the seismic fragility curves of NPP containment structures isolated by LRB, it can be observed that seismic fragility in the case of equivalent linear LRB model are about 5~30 % larger than those in the case of bilinear LRB model.

• 대한조선학회논문집
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• 제51권3호
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• pp.220-230
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• 2014

Typical technical issues associated with Floating LNG (FLNG: FSRU and LNG FPSO) design are categorized in terms of global performance evaluation. Although many proven technologies developed through LNG carrier and oil FPSO projects are available for FLNG design, we are still faced with several technical challenges to clear for successful FLNG projects. In this paper, some of the challenges encountered during development of the floating LNG facility (i.e. LNG FPSO and FSRU) will be reviewed together with their investigated solution. At the same time, research of design improvement including new LNG-related technologies such as combined containment system will be presented to overcome the unrevealed challenges for the FLNG development.