• 한국가스학회지
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• 제27권3호
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• pp.35-40
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• 2023

과충전, 이상 온도 상승 등 이상 상황이 발생하는 조건에서 암모니아 용기의 파열 사고의 예방을 위해서는 용기에 부착된 가용전식 안전밸브의 작동 메카니즘 분석을 통한 사고 예방대책 마련이 필요하다. 본 연구에서는 가압 조건에서 암모니아 용기에 작용하는 응력 분석, 온도 변화에 따른 밀도 변화 분석, 그리고 용기 충전량과 온도 및 압력 변화에 대한 상관관계를 제시하였다. 또한, 암모니아 용기의 최대 충전량을 계산하고, 상평형 선도를 통해 해당 충전량에서의 온도·압력을 산출했다. 이를 바탕으로 가용전식 안전밸브의 적정 용융점을 도출하고 용융 온도 실험을 통해 이를 검증하였다. 이와 같은 연구 결과를 바탕으로 암모니아 용기 파열 사고의 예방을 위한 조건을 제시하였다.

• Journal of Trauma and Injury
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• 제36권3호
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• pp.258-260
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• 2023

Traumatic rupture of the right hemidiaphragm occurred following a high-velocity motor vehicle collision in the case presented herein. The resulting herniation of small bowel loops into the thorax resulted in hemodynamic and respiratory compromise due to pressure effects on the right heart and major vessels. The patient's hemodynamic status improved with reduction of enterothorax, and the diaphragmatic defect was repaired. We discuss the available literature and learning points from this rare case.

• 한국안전학회지
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• 제38권2호
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• pp.8-14
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• 2023

In various industrial sites, piping systems play an essential role in stable fluid supply and pressure maintenance. However, these systems are constantly exposed to risks of earthquakes, explosions, fires, and leaks, which can result in casualties or serious economic losses. With rapid advancements in the industry, different-sized piping systems have been launched; however, there are not enough maintenance personnel for troubleshooting and responding to situations where damages occur to piping systems. This increases the need for introducing autonomous damage management systems. In this study, a lab-based piping system was designed and manufactured by referring to the piping system of a naval ship to analyze the effectiveness of autonomous damage management systems. By using this testbed, a representative algorithm, the hydraulic resistance control algorithm, was realized and examinedIn addition, the difference between the averaged pressure and normalized pressure was introduced to improve the performance of the existing algorithm, which faces some limitations with regard to sensor noise and back pressure from the rupture-simulated pipeline part.

• 한국가스학회지
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• 제26권6호
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• pp.9-15
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• 2022

사용 압력 범위에서 고압 수소 탱크의 내구성을 검증하기 위해서는 수압 파열 시험이 수행되어야 한다. 그런데 물의 초기 주입 과정에서 물과 공기의 상호작용에 의해 생성된 기포가 탱크 내벽에 부착되어 잔류할 경우, 가압된 탱크가 파열되는 과정에서 기포의 급격한 압력 변화로 인해 큰 충격과 소음이 유발된다. 따라서 본 연구에서는 단순화된 수식을 통하여 탱크 내벽에 잔류하는 기포를 제거하기 위해 필요한 유속을 예측하였으며, 수소 버스용수소 용기 형상을 기준으로 해당 유속을 유지하기 위한 주입 노즐의 형상을 결정하였다. 또한 입구 압력에 따른 유속 변화를 예측하기 위하여 수치 해석 모델의 개발이 수행되었고, 예측 결과의 타당성을 입증하기 위하여 모형 제작을 통한 실험이 수행되었다. 실험 결과, 탱크 벽면 근처의 유속은 해석모델 예측 값과 유사하게 나타났으며, 입구 압력이 1.5 ~ 5.5 bar 일 경우 제거 가능한 기포의 최소 크기는 약 2.2 ~ 4.6 mm로 예측되었다.

• 한국분말야금학회:학술대회논문집
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• 한국분말야금학회 2006년도 Extended Abstracts of 2006 POWDER METALLURGY World Congress Part 1
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• pp.627-628
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• 2006

The present work is a study on the argon gas pressure effects of Sinter/HIP sintering on microstructure and strength of different grades of TiC-NiMo cermets. Titanium carbide in the composition of different grades of TiC-NiMo cermets was ranged from 40 to 80 wt.% and the ratio of nickel to molybdenum in the initial powder composition was 1:1, 2:1 and 4:1 respectively. On the sintered alloys, the main strength characteristic, transverse rupture strength (TRS) was measured. Furthermore, the microstructure parameters of some alloys were measured and the pressure effect on pore elimination was evaluated. All the results were compared with common, vacuum sintered alloys. The TRS values of TiC-NiMo cermets could be considerably improved by using Sinter/HIP technique, for high-carbide fraction alloys and for alloys sintered at elevated temperatures.

• Nuclear Engineering and Technology
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• 제53권2호
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• pp.474-483
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• 2021

To establish the exclusive role of hydrogen on burst behaviour of Zircaloy-4 during loss-of-coolant accident transients, an extensive single-rod burst tests were conducted on both unirradiated as-received and hydrogenated Zircaloy-4 cladding tubes at different heating rates and internal overpressures. The visual observations of cladding tubes during bursting as well as post-burst are presented in detail to understand the effect of hydrogen concentration, heating rate, and internal pressure. Impact of hydrogen on burst parameters-burst stress, burst strain, burst temperature-during loss-of-coolant accident transients are compared and discussed. Rupture at multiple locations for hydrogenated cladding at lower internal pressure and higher heating rate is reported for the very first time. A novel burst criterion accounting hydrogen concentration in nuclear fuel cladding is proposed.

• 한국압력기기공학회 논문집
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• 제12권2호
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• pp.58-65
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• 2016

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.

• Nuclear Engineering and Technology
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• 제52권9호
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• pp.2047-2053
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• 2020

Single-tube burst tests on hydrogenated Zircaloy-4 nuclear fuel cladding under simulated loss-of-coolant accident are conducted to evaluate the impact of hydrogen on burst parameters. The heating rate and initial pressure are varied from 5 K/s to 150 K/s and 5 bar-80 bar, respectively. The hydrogen concentration in the cladding is in the range of 0-2000 wppm. Burst stress is lower for hydrogenated cladding in α-phase. A significant loss of ductility is observed in α-phase and lower α + β-phase for hydrogenated cladding. However, the burst strain is higher for hydrogenated cladding in β-phase. There is a sigmoidal dependency of rupture area with initial stress and rupture area is larger for hydrogenated cladding. A novel burst stress correlation for hydrogenated Zircaloy-4 cladding has been proposed.

• 한국원자력학회:학술대회논문집
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• 한국원자력학회 2005년도 추계학술발표회
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• pp.512-513
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• 2005

• 한국가스학회지
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• 제9권2호
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• pp.8-15
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• 2005

주40시간제가 도입되면서 피크닉을 즐기는 세대가 늘어나고 있는 실정이다. 또한 가스에 의한 사고는 토요일과 일요일에 가장 많이 발생하고 있다. 2004년 10월 현재 부탄 캔으로 인한 사고는 전년 동기대비 인명피해가 1.5배로 늘어났다. 본 논문에서는 사용하고 버려지는 부탄 캔의 파열로 인한 과압의 영향에 대하여 Hopkinson의 삼승근법을 이용하여 계산하고,폭발장소 주변의 건축물과 인간에게 미치는 영향을 Probit 모델에 적용하여 피해예측을 평가하였다. Probit 모델에 적용하여 계산하면 50m 이격된 건물에는 손상여부 가능성이 전혀 없는 0$\%$로 나타났으며, 인간에게 미치는 영향은 l0m 이격되면 피해영향이 전혀 없는 것으로 나타났다. 또한 본 논문에서는 폭발효율을 $100\%$적용하여 계산하였다. 따라서 부탄 캔 파열로 인한 실제적인 피해영향은 본 연구에서 계산된 수치보다 더욱더 안전할 것으로 판단된다.