• Journal of Korea Water Resources Association
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• v.42 no.6
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• pp.445-455
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• 2009

In this paper proportional hazards models for the first through seventh break of 150 mm cast iron pipes in a case study area are established. During the modeling process the assumption of the proportional hazards for covariates on the hazards is examined to include the time-dependent covariate terms in the models. As a result, the pipe material/joint type and the number of customers are modeled as time-dependent for the first failure, and for the second failure only the number of customers is modeled as time-dependent. From the analysis on the baseline hazard functions the failure hazards are found to be generally increasing for the first and second failure, while the hazards of the third break and beyond showed a form of a bath-tub. Furthermore, the changes in the baseline hazard rates according to the time and number of break reflect that the general condition of the pipes is deteriorating. The factors causing pipe break and their effects are analyzed based on the estimated regression coefficients and their hazard ratios, and the constructed models are verified using the deviance residuals of the models.

• Nuclear Engineering and Technology
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• v.20 no.4
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• pp.241-245
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• 1988

It is very important to investigate the behaviors of the material parameters governing PCI fuel failure during power ramp because PCI fuel failure is considered to be related to the operations limits of power reactors. In this study, the behavior characteristics of the material parameters such as hoop stress, hoop strain, ridge height, creep strain rate and strain energy in cladding were studied as a function of the operating parameters such as power shock and ramp rate. The FEMAXI-IV fuel rod performance analysis code was used for this study.

• Nuclear Engineering and Technology
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• v.16 no.3
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• pp.169-179
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• 1984

An efficient procedure of evaluating the fuel cladding failures occurring in the normal operations of typical PWR's has been investigated through the analysis of fission product(FP) activities in the reactor coolant using an analytical model, FIPREL code. Performed by this code is an extensive study on the sensivities of FP activities to such physical parameters as enrichment, turnup, and operation temperature of failed fuel rod as well as the effective failure size quantified in terms of the magnitude of gap release coefficient. The results of study are generally in agreement with those by PROFIP method. In the presence of tramp uranium the portion of activities released from failed rod is separated by an iterative calculation based on the activity ratios of fission nuclides chemically more stable than iodines. Obtained are the linear power density and the number of failed rods, the effective failure size, and the mass of tramp uranium. The operation experiences of 4 cycles of Kori Unit 1 are analyzed and the results show that the model is highly reliable for the survey and evaluation of fuel rod conditions during reactor operations.

• Proceedings of the Korean Institute of Information and Commucation Sciences Conference
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• 2022.05a
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• pp.291-295
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• 2022

This paper deal with the advanced thchnology of water supply line breakege detection system in singsan green city. the technology apply for construction eco oriented high-tech city to merge residant, industial, tour reasure parts for songsan green city furture direction achivement and response for a life style change of people in the city. Breakege detection system consist of smart prevention seat, pipeline breakege detection sensor, analysis software, server. etc.. Central control unit sent the data to hwa sung city water supply office by WCDMA in SKY. the data are states about water supply pipeline, Location.etc. This system maintain the long term life cycle of water supply plpeline by the prevention the leakege event through ackonwledge information of evnet occurrence locaion. and used to realtime sense method about demage information of the pipeline and prevent to brekege facilities during excavation work.

• Nuclear Engineering and Technology
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• v.27 no.5
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• pp.775-783
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• 1995

This study is to assess the effects of increasing wall thickness on the safety margin of pressure tube in operating and of lowering initial hydrogen concentration on the DHC growth in respect to the improvement of the reliability of pressure tube in CANDU reactors. The pressure tube with thicker wall of 5.2 mm shows much higher safety margin for flaw tolerance by 25％ than the current 4.2mmm tube. The thicker pressure tubes have a great benefit in LBB assessment including the initial crack depth at which DHC occurs, the crack length at onset of leaking and the available time for action. The resistance for the pressure tube ballooning at LOCA accident is also increased with the thicker tube. The calculations for Heq concentration after 20 years of operation as a function of wall thickness and initial hydrogen concentration show that the 5.2 mm nil thickness tube with 5 ppm initial hydrogen concentration is the most resistant to DHC. with the lower initial hydrogen concentration, TSS temperature for the precipitation or hydride decreases and the crack growth during cooldown reduces.

• Proceedings of the Korean Nuclear Society Conference
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• 1997.05b
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• pp.549-554
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• 1997

원자력발전소 중기발생기 전열관 sleeve의 레이저 보수용접은 원자로 외부의 레이저 광원을 sleeve 내부의 용접 head까지 광섬유로 수백 미터를 전송하여 수행된다. 전열관 레이저용접은 용접 중의 레이저출력, 레이저 전송 광학계의 파손여부, 광학계의 정렬상태 등을 정확히 감시하여 수행하여야 하지만, 작업공간의 협소함과 방사능 구역이라는 어려움 때문에 실시간 감시가 쉽지 않다. 본 연구에서는 광섬유 전송 광학계와 지시용 레이저를 이용하여, 광섬유의 끝단에서 반사된 레이저 빔을 이용하여 광섬유 상태를 실시간 감시할 수 있음을 실험적으로 확인하였다. 실험은 core 직경 800um 의 step index 레이저 전송용 광섬유를 사용하였으며, 광섬유 끝단에 물등의 불순물이 있을 경우와 광섬유가 파손되었을 경우의 감시결과를 얻어, 광섬유 광학계의 실시간 감시가 가능함을 보였다.

• Proceedings of the Korean Nuclear Society Conference
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• 1996.05d
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• pp.176-181
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• 1996

원자로 용기 헤드부위의 관통관은 재질이 Inconel-600이며, 현재 세계각국에서도 원자로 헤드 관통관의 균열이 일부 발견되어 우리나라에서도 관심이 되고 있다. 국내 원전 헤드관 통관 수량도 고리 1,2호기의 경우 40개, 고리3,4호기(영광1,2) 61개, 울진 57개로서 관통관의 균열결함이 존재할 수 있다. 만약 균열이 성장하여 파손 되었을 시 원자로 냉각재 누설등 발전소 안전에 큰영향을 미치므로 균열의 원인으로 알려진 용접부위 잔류응력 및 발전소 정상운전 상태에서의 응력을 해석하였다.

• Journal of the Korean Society for Aeronautical & Space Sciences
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• v.31 no.1
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• pp.25-33
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• 2003

The failure load and mode of the unidirectional and fabric hybrid composite laminate joints are studied by test and finite element analysis. Test is conducted for the specimens with nine various geometries under pin loading. Finite element analysis is performed considering the contact and friction effects between the pin and laminate by MSC/NASTRAN. Failure is estimated by Tsai-Wu and Yamada-Sun criteria on the characteristic curve. While the failure of the specimens with the small width and edge length are much affected by the joint geometry, the geometry effects are negligible in the specimens with large width and edge length. Finite element analysis based on the characteristic length method reasonably predicts the failure load and mode of the joints.

• Magazine of the Korean Society of Hazard Mitigation
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• v.7 no.3
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• pp.48-59
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• 2007

• Proceedings of the Korean Nuclear Society Conference
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• 2001.10a
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• pp.266.1-266
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• 2001