• Proceedings of the KSME Conference
• /
• 2001.11b
• /
• pp.782-787
• /
• 2001

An optimum thermal design analysis of the combined cycle power plant with triple pressure heat recovery steam generator was performed by the numerical simulation. The optimum design module used in the paper is DNCONF, a function of IMSL Library, which is widly known as a method to search for the local optimum. The objective function to be minimized is the cost of total power plant including the steam turbine power enhancement premium. The result of this paper shows that the cost reduces if the design point of power plant becomes the local optimum, and many calculations at various initial conditions should be carried out to get the value near the global optimum.

• Journal of Industrial Technology
• /
• v.26 no.B
• /
• pp.145-155
• /
• 2006

High level of reliability in facility operation is specifically required these days. The goal of this study is to secure a methodology for reliability analysis of hydro-power plant so that an appropriate decision for operation and investment can be made. Fault tree analysis of water supply system within hydro-power plant has been performed in this study. We briefly examined the electric power generation facility and water supply system. We then developed fault tree for the water supply system based on failure modes and effects analysis. We conclude this study and provided future research areas.

• Transactions of the Korean Society of Mechanical Engineers B
• /
• v.28 no.12
• /
• pp.1582-1590
• /
• 2004

The purpose of this study is to show the existence of optimal operation conditions for minimum fuel consumption of the gas turbine based combined cycle cogeneration power plant. Optimal operational condition means the optimal distribution of the power generated by each gas turbine and the heat generated by each HRSG. Total fuel consumption is calculated by the sum of the fuels for gas turbines and supplementary boiler. Fuel consumption is calculated by numerical methods of energy equations which contain the power generated from gas and steam turbines, the heat generated by HRSG and the heat extracted from high pressure steam turbine.

• Journal of the Earthquake Engineering Society of Korea
• /
• v.16 no.3
• /
• pp.35-42
• /
• 2012

We propose a probabilistic method to evaluate the uniform hazard spectra (UHS) of the soil of nuclear power plant(NPP) sites corresponding to that of a bedrock site. To do this, amplification factors on the surface of soil sites were estimated through site response analysis while considering the uncertainty in the earthquake ground motion and soil deposit characteristics. The amplification factors were calculated by regression analysis with spectral acceleration because these two factors are mostly correlated. The proposed method was applied to the evaluation of UHS for the KNGR (Korean Next Generation Reactor) and the APR1400 (Advanced Power Reactor 1400) nuclear power plant sites of B1, B4, C1 and C3. The most dominant frequency range with respect to the annual frequency of earthquakes was evaluated from the UHS analysis. It can be expected that the proposed method will improve the results of integrated risk assessments of NPPs rationally. We expect also that the proposed method will be applied to the evaluation of the UHS and of many other kinds of soil sites.

• Corrosion Science and Technology
• /
• v.16 no.3
• /
• pp.115-127
• /
• 2017

Coal tar-coated pipes buried in a domestic nuclear power plant have operated under the cathodic protection. This work conducted the simulation of the coating performance of these pipes using a FEM method. The pipes, being ductile cast iron have been suffered under considerably high cathodic protection condition beyond the appropriate condition. However, cathodic potential measured at the site revealed non-protected status. Converting from 3D CAD data of the power plant to appropriate type for a FEM simulation was conducted and cathodic potential under the applied voltage and current was calculated using primary and secondary current distribution and physical conditions. FEM simulation for coal tar-coated pipe without defects revealed over-protection condition if the pipes were well-coated. However, the simulation for coal tar-coated pipes with many defects predict that the coated pipes may be severely degraded. Therefore, for high risk pipes, direct examination and repair or renewal of pipes are strongly recommended.

• Nuclear Engineering and Technology
• /
• v.49 no.7
• /
• pp.1563-1570
• /
• 2017

In order to perform dry interim storage and transportation of the spent-fuel assemblies of the Bushehr Nuclear Power Plant, dual-purpose casks can be utilized. The effectiveness of different neutron-shield materials for the dual-purpose cask was analyzed through a set of calculations carried out using the Monte Carlo N-Particle (MCNP) code. The dose rate for the dual-purpose cask utilizing the recently developed materials of $epoxy/clay/B_4C$ and $epoxy/clay/B_4C/carbon$ fiber was less than the allowable radiation level of 2 mSv/h at any point and 0.1 mSv/h at 2 m from the external surface of the cask. By utilization of $epoxy/clay/B_4C$ instead of an ethylene glycol/water mixture, the dose rates on the side surface of the cask due to neutron sources and consequent secondary gamma rays will be reduced by 17.5% and 10%, respectively. The overall dose rate in this case will be reduced by 11%.

• Journal of the KSME
• /
• v.19 no.4
• /
• pp.326-331
• /
• 1979

압력배관에 대한 미국의 국가규준으로는 다음과 같은 것이 있다. Section 1. Power Piping ANSI B31.1 Section 2. Fuol Gas Piping ANSI B31.2 Section 3. Petroleum Refinery Piping ANSI B31.3 Section 4. Liquid Potroleum Transportation Piping ANSI B31.4 5. Section Refrigeration Piping ANSI 31.5 Section 6. Chemical Plant Piping ANSI B31.6 Section 7. Nuclear Power Piping ANSI B31.7 Section 8. Gas Transmission and Distribution Piping Systems ANSI B31.8 이중에서 Power Piping ANSI B31.1은 1977년도에 공진청에서 제정한 "압력배관 기술 기준 (1) "의 기본이 되고 있다. 금반의 냉동배관 기술기준 제정에 있어서도 이것이 압력배관의 범주내에 포함되는 것이기 때문에 기준의 통일성을 기하기 위하여서는 압력 배관기술기준(1)에 준하여 ANSI B31.5 Refrigeration Piping을 기본으로 하여야 할 것으로 고려하였다. 현재 각국의 압력 배관에 대한 기술기준은 그 형식은 여하간에 기본적으로는 ANSI B31. 시리즈에 따르고 있고 또 이 규준이 국제적으로 인정 널리 시행되고 있으므로 본 냉동배관 기술기준도 ANSI B31.5에 따라 제정하는 것이 타당성이 있는 것으로 고려하였다.

• Proceedings of the KSME Conference
• /
• 2008.11b
• /
• pp.2616-2620
• /
• 2008

AOV used fluid capacity and fluid pressure control in nuclear power plant with heating power plant. AOV structures safely must be secured the reliability and a safety of the atomic power plant. but, AOV where is used from domestic is using the product of the overseas enterprise. The AOV design and maintenance technique is insufficient. Therefore According to ASME designed AOV, The performance test resultant fluid leakage did not occur and AOV design was satisfactory.

• Journal of Power System Engineering
• /
• v.7 no.3
• /
• pp.23-28
• /
• 2003

In heavy nuclear power plant, high energy through main steam line is provided to turbine that generate the electric power. Since plant had generated power, high noise has been occurred. Noise make equipments and work environment worse. For finding out the location and the cause of making noise, noise was measured along main steam line at open/close test of Main Steam Isolation Valve (MSIV hereafter). As the result, it was identified that the vortex shedding in the cavity of MSIV is main noise source. The profile change of MSIV seat ring was proposed as the method of noise reduction. After filletting MSIV seat ring, the noise level reduced $10{\sim}20dB$ compared before the change of profile.

• Journal of Drive and Control
• /
• v.11 no.1
• /
• pp.26-34
• /
• 2014