• 상하수도학회지
• /
• 제16권6호
• /
• pp.710-716
• /
• 2002

A General Pipe Break Prediction Model that incorporates linear and exponential models in its form is developed. The model is capable of fitting pipe break trends that have linear, exponential or in between of linear and exponential trend by using a weighting factor. The weighting factor is adjusted to obtain a best model that minimizes the sum of squared errors of the model. The model essentially plots a best curve (or a line) passing through "cumulative number of pipe breaks" versus "break times since installation of a pipe" data points. Therefore, it prevents over-predicting future number of pipe breaks compared to the conventional exponential model. The optimal replacement time equation is derived by using the Threshold Break Rate equation by Loganathan et al. (2002).

• Structural Engineering and Mechanics
• /
• 제5권2호
• /
• pp.149-165
• /
• 1997

A dynamic time-history analysis of the coupled internals and core in the vertical direction is performed as a part of the fuel assembly qualification program. To reflect the interaction between the fuel rods and grid cage, friction element is developed and is implemented. Also derived here is a method to calculate a hydraulic force on the reactor internals due to pipe break. Peak responses are obtained for the excitations induced from earthquake and pipe break. The dynamic responses such as fuel assembly axial forces and lift-off characteristics are investigated.

• 한국수자원학회논문집
• /
• 제42권7호
• /
• pp.525-535
• /
• 2009

본 연구에서는 상수관망에서 개별적으로 노후도가 심하여 개량이 필요한 구간을 보다 정확하게 구분하기 위해 새로운 개별관로 정의 방법이 개발되었다. 적절한 관로 최소구성성분 길이를 결정하기 위하여 여러 가지 관로 최소구성성분 길이에 대한 평균 누적파손횟수경사선의 분산값을 비교하여 가장 큰 분산값을 나타내는 관로 최소구성성분 길이인 4 m 를 연구대상 지역의 상수관망에 적용하였으며 관로 ID는 39개로 구분되어졌다. 관로의 경제적 최적교체 시기는 한계파손율과 관로의 파손경향모형을 이용하여 결정되었는데, 각 관로 ID에 대하여 관로의 선형적 파손경향, 지수적 파손경향 또는 선형과 지수형 사이에 있는 파손경향 모두에 적용될 수 있는 General Pipe Break Prediction Model(Park and Loganathan, 2002)과 수정된 시간척도를 이용한 ROCOF(Park et al., 2007)를 적용하여 연구대상 상수관망의 최적교체시기를 산정 및 분석하였다. ROCOF 모형화 과정에서 대수-선형과 와이블 ROCOF를 적용 후 최대로그우도 추정값을 비교하여 최대로그우도가 큰 값을 가지는 ROCOF를 각 관로 ID의 ROCOF로 사용하였다. 관로파손으로 인한 사회적 비용이 관로의 최적교체시기에 미치는 영향도 분석되었다.

• 상하수도학회지
• /
• 제23권3호
• /
• pp.305-313
• /
• 2009

This paper provides a method for evaluating a residual life of water mains using a proportional hazard model(PHM). The survival time of individual pipe is defined as the elapsed time since installation until a break rate of individual pipe exceeds the Threshold Break Rate. A break rate of an individual pipe is estimated by using the General Pipe Break Model(GPBM). In order to use the GPBM effectively, improvement of the GPBM is presented in this paper by utilizing additional break data that is the cumulative number of pipe break of 0 for the time of installation and adjusting a value of weighting factor(WF). The residual lives and hazard ratios of the case study pipes of which the cumulative number of pipe breaks is more than one is estimated by using the estimated survival function. It is found that the average residual lives of the steel and cast iron pipes are about 25.1 and 21 years, respectively. The hazard rate of the cast iron pipes is found to be higher than the steel pipes until 20 years since installation. However, the hazard rate of the cast iron pipes become lower than the hazard rates of the steel pipes after 20 years since installation.

• 한국압력기기공학회 논문집
• /
• 제13권1호
• /
• pp.54-60
• /
• 2017

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%.

• Nuclear Engineering and Technology
• /
• 제55권5호
• /
• pp.1604-1615
• /
• 2023

In an open-pool type research reactor with a downward forced flow in the core, pipes can be under sub-atmospheric pressure because of the large pressure drop at the reactor core in the atmospheric pool. Sub-atmospheric pressure can result in air inflow into the pipe from the pressure difference between the atmosphere and the inside of the pipe, which in a postulated pipe break scenario can lead to the breakdown of the cooling pump. In this study, a plant-scale experiment was conducted to study air inflow in large piping systems by considering the actual operational conditions of an advanced research reactor. The air inflow rate was measured, and the entrained air was visualized to investigate the behavior of air inflow and flow regime depending on the pipe break size. In addition, the developed drift-flux model for a large vertical pipe with a diameter of 600 mm was compared with other correlations. The flow regime transition in a large vertical pipe under downward flow was also studied using the newly developed drift-flux model. Consequently, the characteristics of two-phase flow in a large vertical pipe were found to differ from those in small vertical pipes where liquid recirculation was not dominant.

• Nuclear Engineering and Technology
• /
• 제25권2호
• /
• pp.204-214
• /
• 1993

본 논문은 원자력발전소의 배관설계에 파단전 누설(leak-before-break : LBB) 개념이 적용됨에 따라 새롭게 해석대상이 된 분기관파단에 의한 노심지지배럴의 쉘응답을 계산한 것이다. 앞으로 직경 10인치 이상의 고에너지 배관에 대해 LBB 개념이 적용될 것으로 예상되는 바, 이 경우 LBB 적용대상에서 제외되는 유일한 1차측 배관인 3인치 가압기 분무관의 파단을 가정하였고 이때 노심 지지배럴에 가해지는 쉘응답을 구하였다. 이들 응답을 직경 10인치 이상인 배관파단시의 응답과 비교한 결과 앞으로 직경 10인치 이상의 배관에 대해 LBB 개념이 적용될 경우 배관파단에 대한 노심지지배럴의 쉘응답은 무시할 수 있음을 보였다.

• 한국수자원학회논문집
• /
• 제42권6호
• /
• pp.457-464
• /
• 2009

본 논문에서는 상수관로의 파손자료를 이용하여 관로의 위험률을 산정하기 위해 사용되는 비례위험모형의 관로의 순차적 파손시간 예측정확도를 분석하고 이를 이용하여 관로의 경제적 교체 시간구간을 산정할 수 있는 방법론을 제시하였다. 비례위험모형에 기초한 생존함수를 이용하여 연구대상 관로들의 순차적 파손시간을 예측하고 이들을 기록된 파손시간과의 차이를 분석하였다. 이를 통하여 비례위험모형의 파손시간 예측 오차를 최소화하는 생존확률은 0.70인 것으로 결정되었으며, 세 번째 파손으로부터 일곱 번째 파손에 대한 모형만이 관로의 파손시간을 예측하는데 적합한 것으로 분석되었다. 생존확률 0.70과 순차적 파손사건에 대한 생존함수의 하한 및 상한을 이용하여 예제로 사용된 관로에 대해 예측된 파손시간의 95% 신뢰구간의 하한 및 상한을 추정하였다. 예측된 파손시간의 95% 신뢰 구간의 하한과 상한을 이용하여 관로 파손 경향모형인 General Pipe Break Prediction Models(GPBM)을 구축하고 이들을 관로의 한계파괴율과 결합하여 시간에 대한 해를 구하므로써 경제적 교체 시간구간을 산정하였다.

• Nuclear Engineering and Technology
• /
• 제50권5호
• /
• pp.758-766
• /
• 2018

We developed numerical models to efficiently simulate the low-cycle fatigue behavior of a pipe elbow. To verify the model, in-plane cyclic bending tests of pipe elbow specimens were conducted, and a through crack occurred in the vicinity of the crown. Numerical models based on the erosion method and tie-break method are developed, and the numerical results are compared with experimental results. The calculated results of both models are in good agreement with experimental results, and the model using the tie-break method possesses two times faster calculation speed. Therefore, the numerical model based on the tie-break method would be beneficial to evaluate the strength of piping systems under seismic loadings.

• International Journal of Safety
• /
• 제3권1호
• /
• pp.53-58
• /
• 2004

SMART-P is a promising advanced small and medium category nuclear power reactor. It is an integral type reactor with a sensible mixture of new innovative design features and proven technologies aimed at achieving a highly enhanced safety and improved economics. The enhancement of the safety and reliability is realized by incorporating inherent safety improving features and reliable passive safety systems. The improvement in the economics is achieved through a system simplification, and component modularization. Preliminary safety analyses on selected limiting accidents confirm that the inherent safety improving design characteristics and the safety system of SMART-P ensure the reactor's safety. SMART-P is an advanced integral pressurized water reactor. The purpose of this study is for the safety analysis of the steam generator module pipe break for the SMART-P. The integrity of the fuel rod is the major criteria of this analysis. As a result of this analysis, the safety of the RCS and the secondary system is guaranteed against the module pipe break of a steam generator of the SMART-P.