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최청열,오세홍,최대경,김원태,장윤석,김승현,Choi, Choengryul,Oh, Se-Hong,Choi, Dae Kyung,Kim, Won Tae,Chang, Yoon-Suk,Kim, Seung Hyun 한국압력기기공학회 2016 한국압력기기공학회 논문집 Vol.12 No.2
Since, in case of high energy piping, steam jets ejected from the rupture zone may cause damage to nearby structure, it is necessary to design it into consideration of nuclear power plant design. For the existing nuclear power plants, the ANSI / ANS 58.2 technical standard for high-energy pipe rupture was used. However, the US Nuclear Regulatory Commission (USNRC) and academia recently have pointed out the non-conservativeness of existing high energy pipe fracture evaluation methods. Therefore, it is necessary to develop a highly reliable evaluation methodology to evaluate the behavior of steam jet ejected during high energy pipe rupture and the effect of steam jet on peripheral devices and structures. In this study, we develop a method for analyzing the impact load of a jet by high energy pipe rupture, and plan to carry out an experiment to verify the evaluation methodology. In this paper, the basic data required for the design of the jet impact load experiment equipment under construction, 1) the load change according to the jet distance, 2) the load change according to the jet collision angle, 3) the load variation according to structure diameter, and 4) the load variation depending on the jet impact position, are numerically obtained using the developed steam jet analysis technique.
원전 내 배관의 증기 누설 사고 시 누설 탐지 포집/이송 시스템 예비 해석
최대경,최청열,권태순,어동진,Choi, Dae Kyung,Choi, Choengryul,Kwon, Tae-Soon,Euh, Dong-Jin 한국압력기기공학회 2020 한국압력기기공학회 논문집 Vol.16 No.2
As leakage in nuclear power plants could cause a variety of problems, it is very critical to monitor leakage from the safety point of view. Accordingly, a new type of leak detection system is currently being developed and flow characteristics of the sampling and transportation system are investigated by using numerical analysis as a part of the development process in this study. The results showed that the steam mass fraction varied according to the effect of the gap between the insulation and piping component, transportation velocity, and material properties of porous media during the sampling and transportation process. The results of this study should be useful for understanding flow characteristics of the sampling and transportation system and its design and application.
고에너지배관 파단위치에 따른 배관휩과 충격파의 영향 평가
김승현,장윤석,최청열,김원태,Kim, Seung Hyun,Chang, Yoon-Suk,Choi, Choengryul,Kim, Won Tae 한국압력기기공학회 2017 한국압력기기공학회 논문집 Vol.13 No.1
When a sudden rupture occurs in high energy lines, ejection of inner fluid with high temperature and pressure causes blast wave as well as thrust forces on the ruptured pipe itself. The present study is to examine pipe whip behaviors and blast wave phenomena under postulated pipe break conditions. In this context, typical numerical models were generated by taking a MSL (Main Steam Line) piping, a steam generator and containment building. Subsequently, numerical analyses were carried out by changing break locations; one is pipe whip analyses to assess displacements and stresses of the broken pipe due to the thrust force. The other is blast wave analyses to evaluate the broken pipe due to the blast wave by considering the pipe whip. As a result, the stress value of the steam generator increased by about 7~21% and von Mises stress of steam generator outlet nozzle exceeded the yield strength of the material. In the displacement results, rapid movement of pipe occurred at 0.1 sec due to the blast wave, and the maximum displacement increased by about 2~9%.
OPR1000 원자로 격납건물 내 중대사고 시 수소 및 증기 거동에 대한 CFD 해석
홍태협(Tae Hyub Hong),최청열(Choengryul Choi),김형택(T. H. Kim) 대한기계학회 2011 대한기계학회 춘추학술대회 Vol.2011 No.10
Hydrogen could be generated by an active reaction of the fuel-cladding and the steam in the reactor pressure vessel during a hypothetical severe accident in a nuclear power plant (NPP). In such situation, the generated hydrogen is released together with steam into the containment. In order to mitigate hydrogen hazards which could possibly occur in the NPP containment, a hydrogen mitigation system (HMS) is usually adopted, such as hydrogen igniters and passive autocatalytic recombiners (PAR). In this study, an analysis of the hydrogen and steam behavior has been numerically performed using fully 3-dimensional computational fluid dynamics (CFD) technique, during a total loss of feed water (LOFW) accident in the OPR1000 containment. During the accident, a huge amount of hot water, steam, and hydrogen are released into the containment. The possibilities of flame acceleration and a transition from deflagration to detonation (DDT) are evaluated by using the Sigma?ambda criteria.