• Journal of Energy Engineering
• /
• 제16권3호
• /
• pp.103-112
• /
• 2007

Flood issue for nuclear power plants designed and built in 1970 is extremely severe for main steam header compartment and main feedwater line region of intermediate building and lower floor. A calculation for flood level at the main feedwater line isolation compartment is now performing by hand calculation. But, this methodology is quite conservative assumption. The goal of this study was to develop method to analyze flowrate using the RETRAN-3D computer code, and the developed method was applied to flood level analysis following main feedwater line break. As a result of analysis, flood level was low remarkably.

• Transactions of the Korean Society of Pressure Vessels and Piping
• /
• 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%.

• Computational Structural Engineering
• /
• 제6권4호
• /
• pp.73-82
• /
• 1993

Investigated in this paper is the effect of fluid-structure interaction between reactor internal components due to their immersion in a confining fluid on the dynamic responses. A non-linear mathematical model is developed for the dynamic analysis of the reactor internals, which includes lumped masses, stiffnesses and hydrodynamic couplings. The hydrodynamic mass matrix which characterizes the fluid-structure interaction is calculated. Also, the equations of motion containing hydrodynamic mass matrix are presented. The responses of the reactor internals due to seismic and pipe break excitations are obtained for the case of with- and without-hydrodynamic couplings and the different response characteristics are investigated.

• Proceedings of the Korean Nuclear Society Conference
• /
• 한국원자력학회 2002년도 춘계공동학술발표회요약집
• /
• pp.148.2-148
• /
• 2002

• Proceedings of the KSME Conference
• /
• 대한기계학회 2005년도 창립60주년 기념 추계 학술대회
• /
• pp.143.2-143.2
• /
• 2005

• 한국IT서비스학회:학술대회논문집
• /
• 한국IT서비스학회 2008년도 추계학술대회
• /
• pp.469-471
• /
• 2008

원자력발전소에는 매우 복잡하고 긴 배관 시스템이 작동되고 있다. 이 배관은 매우 높은 온도와 압력에 견디게 설계 및 제작 되었으나, 사용연수의 증가에 따라 배관이 깎이는 감육현상이 발생하며, 이로 인한 배관 파단 사고가 발생하고 있다. 이러한 감육현상은 배관의 곡관부에서 자주 발생하는데, 이를 감시하기 위하여 지금까지는 초음파를 이용한 배관 두께 측정을 해오고 있다. 그러나 이 검사 결과의 신뢰성이 없고, 유선 검사 방식을 채택함으로 인한 장비 설치 문제로 극히 일부 배관의 곡관부에 대한 감시만 수행되고 있는 문제가 있다. 본 논문에서는 펄스 와전류 기법과 일체형 소형 무선 센서를 이용하여 이러한 문제를 해결할 수 있는 방안을 제안한다.

• Proceedings of the Korean Nuclear Society Conference
• /
• 한국원자력학회 2003년도 춘계학술발표대회 요약집
• /
• pp.405.1-405.1
• /
• 2003

• Proceedings of the Korean Nuclear Society Conference
• /
• 한국원자력학회 2002년도 춘계공동학술발표회요약집
• /
• pp.171.2-171
• /
• 2002

• Transactions of the Korean Society of Mechanical Engineers A
• /
• 제35권6호
• /
• pp.651-659
• /
• 2011

With the increase in the thermal power output of recently developed nuclear power plants, the applied forces and moments are increased in some piping systems, so that the leak-before-break (LBB) application criteria would not be satisfied in those pipes. In this paper, we present a method for obtaining the additive LBB margin in the pipes by considering the nonlinearity of the crack and material properties. Finite element analysis and the moment-rotation equation of beam theory were used to calculate the nonlinearity of the crack and material properties. Moreover crack stability analysis was performed using the method proposed in this study. The LBB margin was increased effectively through consideration of the nonlinearity of the crack and material properties in the pipe.

• Journal of the Korean Society for Nondestructive Testing
• /
• 제33권2호
• /
• pp.138-146
• /
• 2013

The present paper provides the elastic stress intensity factors(SIFs) of thick-walled cylinder with non-idealized circumferential through-wall cracks. For estimating these elastic SIFs, the systematic three-dimensional(3D) elastic finite element(FE) analyses were performed. In order to consider practical shape of thick-walled cylinder and non-idealized circumferential through-wall crack, the values of thickness of cylinder, reference crack length and crack length ratio were systematically varied. As for loading conditions, axial tension, global bending and internal pressure were considered. In particular, in order to calculate the SIFs of thick-walled cylinder with non-idealized circumferential through-wall crack from those of thick-walled cylinder with idealized circumferential through-wall crack, the correction factor representing the effect of non-idealized crack on the SIFs were proposed in this paper. The present results can be applied to accurately evaluate the rupture probabilities of nuclear piping considering actual crack growth behaviors.