• Journal of Chest Surgery
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• 제23권5호
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• pp.905-915
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• 1990

A clinical evaluation was performed on 545 cases of the chest trauma those had been admitted and treated at the department of thoracic and cardiovascular surgery in Chosun University Hospital during the past 11 years 5 months period from January 1978 to may 1989. Obtained results were as follows: 1. The ratio of male to female was 3.9: 1 in male predominance, and the majority[66.6%] was distributed from 3rd to 5th decade. 2. Nonpenetrating chest trauma was more common than penetrating about 4.6 times, and the most common cause of the nonpenetrating injuries was traffic accident[241/448, 53.8%] and of the penetrating injuries was stab wound[88/97, 90.7%]. 3. Only 79 cases[14.5%] were arrived to our emergency room within one hour after trauma. 4. The most common lesion due to trauma among these admitted patients was rib fracture[390/545, 71.6%], and the others were lung contusion[217/545, 39.8%], hemothorax[35%], hemopneumothorax[19.6%], and pneumothorax[11.8%] et al in decreasing order. 5. The associated injuries those required special treatment of other departments were 223 cases and its distributions were bone fractures[178/545, 32.7%], head injury[5.3%], and abdominal injury[6.6%]. 6. The others, but interesting chest injuries were follows: sternum fracture[3.1%], diaphragm rupture[2.6%], myocardial laceration and rupture[2 cases], bronchial rupture and laceration[2 cases], and traumatic thymoma rupture[1 case]. 7. The incidence of flail chest was 5.8%a[26/448] in the nonpenetrating injury, and the causes were multiple rib fracture which was in rows more than 4 rib fracture[20 cases], and sternum fracture[6 cases]. 8. We could managed the most of the patient with conservative treatment[43.1%] or closed tube thoracostomy[52.7%], but required emergency open thoracotomy in 64 cases

• 대한기계학회:학술대회논문집
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• 대한기계학회 2007년도 춘계학술대회B
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• pp.2775-2780
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• 2007

The ballistic range has long been employed in a variety of engineering fields such as high-speed impact engineering, projectile aerodynamics and aeroballistics, since it can create very high-pressure states in a short time. Since the operation of the ballistic range includes many complicated processes, each should be studied in detail for the best operation of the device. One of the main processes which have a major influence in its operation is the compression of the driver gas. Most of the studies available in this field hardly discuss this process in detail and thus lack a proper understanding of its effect. In the present study, a computational analysis has been made to investigate the compression process in the pump tube of a ballistic range. The results obtained are validated with some experimental data. It is seen that the pump tube parameters and the piston mass significantly affect the compression process and the time to build up the required diaphragm rupture pressure.

• Tribology and Lubricants
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• 제17권6호
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• pp.453-458
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• 2001

The fretting wear of a nuclear fuel rod it a dangerous phenomenon. In this study, TiN coating was used to reduce the fretting wear of Zircaloy-4 tube, a nuclear fuel rod cladding material. TiN coating is probably one of the molt frequently and successfully used PVD coatings for the mitigation of fretting wear. The fretting tester was designed and manufactured for this experiment. The number of cycles, slip amplitude and normal load were selected as main factors of fretting wear. The results of this research showed that wear volume was improved 1.3∼3.2 times with TiN coating. The worn surfaces were observed by SEM. Wear mechanism at lower slip amplitude was the brittle cracks and rupture of TiN coating. However, adhesive and abrasive wear were mainly observed on most surfaces at higher slip amplitude.

• 한국연소학회:학술대회논문집
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• 한국연소학회 2015년도 제51회 KOSCO SYMPOSIUM 초록집
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• pp.147-150
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• 2015

When high-pressure gas is suddenly leaked out into the air, unexpected ignition occurs without any external ignition source. Until now, there have been investigations on self-ignition of hydrogen by supplying high-pressure hydrogen gas into a tube. However the mechanism of hydrogen ignition is still unclear. This paper describes the area-ratio effect on hydrogen ignition by inserting a brass plate. The results show that the ignition phenomena differ as the area-ratio changed. Also, the rupture pressure for self-ignition has to be higher.

• 소음진동
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• 제9권2호
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• pp.285-294
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• 1999

Transient analysis for compressible fluid flow has been performed experimentally and analytically to study the dynamic characteristics of the end volume transmission lines following a sudden pressure change a its entrance. The numerical method was developed based on the method of characteristics. The sudden pressure at its entrance was generated by rupture of diaphragm in a shock tube. The sudden pressure was used to obtain the response, as input signal for the numerical analysis. The response to the sudden pressure at the end volume was measured using a pressure transducer. The experimental result shows good agreements with the numerical result. The effects of tube length, its diameter and end volume magnitude are evaluated on the responses of the pressure and on the damping factor. It is found that the viscous damping effects on the response through the transmission pipeline becomes larger with increasing pi;eline length and decreasing diameter of the pipe and the fluid-elastic stiffness decreases with increasing the terminal volume. The numerical approach presented in this paper can be very useful in designing the instrument and control system.

• 플랜트 저널
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• 제17권1호
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• pp.38-49
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• 2021

발전소 효율증대로 인해 610℃까지 높아진 증기온도는 보일러 튜브의 내구성을 저하시키고 있으며 여기에 저열량탄 사용증가로 후부연소 및 지연연소 현상이 가중됨에 따라 최종재열기의 과열과 튜브 파열사고가 빈번해지고 있다. 최종 재열기 과열을 방지하고자 과열저감수 주입량이 늘어났으며 이는 보일러 효율저하로 이어지고 있다. 그동안 보일러 튜브온도를 전체가 아닌 튜브 개별적으로 제어하기 위한 노력이 계속되어 왔지만 성공사례가 알려진 바가 없다. 이번 연구에서는 과열된 일부 튜브그룹에 다공판을 설치하여 가스흐름에 저항을 줌으로써 연소가스량을 저감시켜 튜브의 온도를 낮추고 저감된 연소가스는 인접한 곳으로 이동하여 다른 튜브의 온도를 높이는 것이다. 연구결과 튜브간 온도편차가 1.5℃ 감소하였고 과열저감수 주입량이 6,929 kg/h 감소하였으며 튜브 최고온도를 623.4℃까지 경감하였다. 이는 관리기준온도인 630℃에 6.6℃ 여유가 있는 수치이다.

• 대한기계학회:학술대회논문집
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• 대한기계학회 2003년도 추계학술대회
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• pp.1186-1191
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• 2003

The 40% of wall criterion, which is generally used for the plugging of steam generator tubes, may be applied only to a single crack. In the previous study, a total of 9 failure models were introduced to estimate the local failure of the ligament between cracks and the optimum coalescence model of multiple collinear cracks was determined among these models. It is, however, known that parallel axial cracks are more frequently detected during an in-service inspection than collinear axial cracks. The objective of this study is to determine the plastic collapse model which can be applied to the steam generator tube containing two parallel axial through-wall cracks. Nine previously proposed local failure models were selected as the candidates. Subsequently interaction effects between two adjacent cracks were evaluated to screen them. Plastic collapse tests for the plate with two parallel through-wall cracks and finite element analyses were performed for the determination of the optimum plastic collapse model. By comparing the test results with the prediction results obtained from the candidate models, a plastic zone contact model was selected as an optimum model.

• Nuclear Engineering and Technology
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• 제32권5호
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• pp.465-476
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• 2000

In a nuclear power plant, steam generator tubes cover a major portion of the primary pressure-retaining boundary. Thus very conservative approaches have been taken in the light of steam generator tube integrity According to the present criteria, tubes wall-thinned in excess of 40% should be plugged whatever causes are. However, many analytical and experimental results have shown that no safety problems exist even with thickness reductions greater than 40%. The present criterion was developed about twenty years ago when wear and pitting were dominant causes for steam generator tube degradation. And it is based on tubes with single cracks regardless of the fact that the appearance of multiple cracks is more common in general. The objective of this study is to review the conservatism of the present plugging criteria of steam generator tubes and to propose a new coalescence model for two adjacent through-wall cracks existing in steam generator tubes. Using the existing failure models and experimental results, we reviewed the conservatism of the present plugging criteria. In order to verify the usefulness of the proposed new coalescence model, we performed finite element analysis and some parametric studies. Then, we developed a coalescence evaluation diagram.

• 한국안전학회지
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• 제20권2호
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• pp.32-37
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• 2005

The purpose of this study is for the sensitivity study f9r a Steam Generator Tube Rupture (SGTR) of the System-integrated Modular Advanced ReacTor for a Pilot (SMART-P) plant. The thermal hydraulic analysis of a SGIR for the Limiting Conditions for Operation (LCO) is performed using TASS/SMR code. The TASS/SMR code can calculate the core power, pressure, flow, temperature and other values of the primary and secondary system for the various initiating conditions. The major concern of this sensitivity study is not the minimum Critical Heat Flux Ratio(CHFR) but the maximum leakage amount from the primary to secondary sides at the steam generator. Therefore the break area causing the maximum accumulated break flow is researched for this reason. In the case of a SGIR for the SMART-p, the total integrated break flow is 11,740kg in the worst case scenario, the minimum CHFR is maintained at Over 1.3 and the hottest fuel rod temperature is below 606"I during the transient. It means that the integrity of the fuel rod is guaranteed. The reactor coolant system and the secondary system pressures are maintained below 18.7MPa, which is system design pressure.

• Nuclear Engineering and Technology
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• 제27권4호
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• pp.483-490
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• 1995

PKL III A 4.4 실험은 "증기발생기 세관파열사고 후 소외전원 가용의 조건 하에서 발전소가 비상냉각수 주입없이 수작동에 의해 제어될 수 있음을 확인하는 것이다. 실험 모사에 따른 NLOOP Code의 제한이나 능력의 검증을 위해, 실험에서 얻어진 PKL 설비의 거동은 NLOOP의 결과와 상호 비교되었다. NLOOP 코드는 한국원자력연구소와 독일 SIEMENS/KWU사에 의해 Westinghouse 형 발전소의 과도현상 해석용으로 개발되었으며, PKL III 설비모사를 위해 적절히 수정되었다. 자연대류에 의한RCS Loop의 냉각수 유량과 격리된 RCS Loop에서의 자연대류 중단현상을 특별히 주의깊게 연구하였다. 실험과 계산 결과의 비교는 NLOOP 코드의 의사능가 문제점들을 보여준다.보여준다.