• Proceedings of the KSME Conference
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• 2001.06a
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• pp.322-327
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• 2001

The internal leaks of RCS pressure boundary valves may cause thermal fatigue crack because of the TASCS in RCS branch line. After experienced unisolable piping failures in several PWR plants, many studies have peformed to understand these phenomena and various methods were applied to ensure the structural integrity of piping. In this paper, the cause of unisolable piping failures and the alternatives to prevent recurrence of failure were reviewed. Also, the severity of piping failure including susceptibility of valve leaks was evaluated for the Westinghouse 2-loop plant. The length of turbulent penetration on RHR inlet piping was measured and, thermal fluid analysis and fatigue analysis was performed for this piping. As a means of ensuring the structural integrity, temperature monitoring and specialized UT and other alternatives were compared for the further application.

• Proceedings of the Korean Society of Propulsion Engineers Conference
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• v.y2005m4
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• pp.423-426
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• 2005

Numerical analysis of a gaseous jet injected into a closed nozzle was carried out considering the valve operation to simulate the interior pressure development of closed nozzle. Pressure data was obtained through valve operation and we compared numerical analysis with experiment data. Commercial code was used for the present calculation. Numerical results of a pressure development since its start showed good agreement for experiment data of the nozzle operation.

• Proceedings of the Korean Nuclear Society Conference
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• 1999.10a
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• pp.341.1-341
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• 1999

• Journal of Energy Engineering
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• v.24 no.2
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• pp.40-44
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• 2015

Sensitivity on the reactor safety was evaluated for the safety margin and time delay applied to the opening pressure of liquid relief valve(LRV) of the primary heat transport system(PHTS) in the pressurized heavy water reactor(PHWR) type nuclear power plant. Since the LRV is the pressure boundary for the PHTS in the safety analysis, the operating of LRV has a significant effect on the safety analysis results. Therefore it is required during the regulatory review of Wolsong Unit 1 safety analysis to find the safety effect of the application of safety margin and time delay to the LRV opening pressure for the safety analysis of PHTS pressurizing events.

• Journal of the Korean Institute of Gas
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• v.22 no.1
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• pp.60-63
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• 2018

This paper presents the FEM analysis results on the strength safety of a gas valve for a LPG cylinder. Based on the FEM analysis, the maximum von Mises stress on the boundary zone between a safety valve and the upper area of the thread is 99.2 MPa for the supplied gas pressure of 3.5 MPa in which the gas valve is fully opened. The maximum von Mises stress of 99.2 MPa is considered as safety value, because that value is lower than the yield stress of a brass material. In this case, the maximum deformation at the upper right part of the pressure regulator is 0.002mm. The maximum deformation zone is not a meaning part of the sealing part such as an O-ring or a diaphragm of a gas valve and a pressure regulator. The proposed hybrid gas valve model in which is integrated with a conventional cut-off valve and a pressure regulator is recommended as a gas leakage free mechanism and minimized compact size for a LPG cylinder.

• Aerospace Engineering and Technology
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• v.11 no.2
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• pp.109-116
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• 2012

A vent-relief valve performs as a safety-valve assembly for liquid propellant feeding system of space launch vehicle, which relives pressurant propellant tanks during the filling and the flight. At vent mode, valve is opened and closed by driving pneumatic pressure, and at relief mode, valve is automatically operated to set relief pressure. In this study, we have analyzed a basic layout of vent-relief valve which is designed using foreign LVs(Saturn) to satisfy requirements of Korean Space Launch Vehicle. The simulation model of vent-relief valve is designed by using the AMESim code to verify design parameters and evaluate pneumatic behaviors of valve. In this study, we performed dynamic characteristic simulations on design parameters. And we could predict opening/closing time and pressures, operating performances on design parameters. Using this results, we could suggest detail design and boundary conditions of design.

• Proceedings of the Korean Nuclear Society Conference
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• 1996.11a
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• pp.369-375
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• 1996

가압경수로의 기동과 냉각시 발생할 수 있는 저온과압사고는 원자로 압력용기의 취성파괴를 유발할 위험이 있다. 따라서 발전소는 저온과압을 방지하기 위해 기술지침서의 온도-압력 곡선을 토대로 운전온도에 따른 압력경계를 제한하고 있으며, 과압방지설비로 가압기 PORV나 잔열제거계통의 방출밸브를 갖추고 있다. 미 NRC에서는 GL90-06을 통해 저온과압사고에 대한 안전성 분석을 권고하고 있으며, 이에 따른 표준 기술 지침서를 제시하였다. 국내 가동 원자력발전소중 영광 3,4호기 이후에는 설계시 이를 반영하였으나, 타 발전소에는 반영되질 않았다. 이 논문에서는 이들 운전중인 가압경수로의 저온과압사고에 대한 안전성 분석을 수행하기 위해 개발한 안전성 평가 방법을 제시하였다.

• Proceedings of the Korean Society of Propulsion Engineers Conference
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• 1998.04a
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• pp.19-19
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• 1998

최근 화학, 연소, 동력, 제철 등의 각종 플랜트에서 조업압력이 고압화되어 가고 있으며, 이에 수반하여 배관계를 통하는 고압가스 유동에 관한 연구가 활발하게 진행되고 있다. 배관계를 통하는 고압가스의 유동에 있어서 유량의 적절한 제어, 유동에 의하여 야기되는 배관계의 소음·진동, 그리고 배기가스의 적절한 처리법 등은 공학적으로 매우 중요한 문제로 알려져 왔다. 일반적으로 정상운전을 하는 플랜트에서 고압 배기가스의 문제는 배기가스 Expander에 의하여 에너지를 회수하는 방법이 생각될 수 있으나, 실제 공업현장에서는 배기가스를 안전하고, 또 소음·진동을 발생시키지 않도록 적절하게 처리하는 것이 매우 중요한 기술적 과제로 남아 있다. 일반적으로 배기가스의 압력이 임계압력(critical pressure) 이상으로 되는 경우(실제 대부분의 플랜트에서 배기가스의 압력은 임계압력보다 매우 높다), 배관계 내부에서 충격파(shock-wave)가 발생하여 난류와동 혹은 난류경계층과 간섭하게 됨으로써 강력한 공기역학적 소음이나 진동을 발생시키게 된다. 이와 같은 소음·진동에 대한 대책으로는 현재 가스배출부에 감압밸브를 직렬로 설치하거나, 유로에 다공판(porous plates)들을 삽입하여 감압과정을 공간적으로 분산시킴으로써, 충격파가 발생하지 않도록 하는 방법을 주로 채택하고 있다. 그러나 이러한 방법을 적용하는 경우 배기가스 유동에 대한 유량의 제어기능이 저하되는 문제가 발생한다.

• Journal of Energy Engineering
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• v.7 no.2
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• pp.202-208
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• 1998

As in the other industrial processes, a nuclear power plant involves a steam relieving process through which condensable steam is discharged and condensed in a subcooled pool. An analysis of steam discharge transients was carried out using the method of characteristics to determine the flow characteristics and dynamic loads of piping that are used for structural design of the piping and its supports. The analysis included not only the steam flow rate but also the flow rates of the air and water which originally exist in the pipe. The analytical model was developed for a uniform pipe with friction through which the flow was discharged into a suppression pool. Including the combinations of system elements such as reservoir, valve and branching pipe lines. The piping flow characteristics and dynamic loads were calculated by varying system pressure, pipe length, and submergence depth. It was found that the dynamic load, water clearing time and water clearing velocity at the water/air interface were dependent not only on the system pressure and temperature but also on the pipe length and submergence depth.

• Transactions of the Korean Society of Mechanical Engineers B
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• v.20 no.6
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• pp.1921-1930
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• 1996

To design an optimum engine intake system, a flow model for the intake manifold was developed by the finite difference method. The flow in the intake manifold was one-dimensional, and the finite difference equations were derived from governing equations of flow, continuity, momentum and energy. The thermodynamic properties of the cylinder were found by the first law of thermodynamics, and the boundary conditions were formulated using steady flow model. By comparing the calculated results with experimental data, the appropriate boundary conditions and convergence limits for the flow model were established. From this model, the optimum manifold lengths at different engine operating conditions were investigated. The optimum manifold length became shorter when the engine speeds were increased. The effect of intake valve timings on inlet air mass was also studied by this model. Advancing intake valve opening decreased inlet air mass slightly, and the optimum intake valve closing was found. The difference in inlet air mass between cylinders was very small in this engine.