• Journal of Energy Engineering
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• v.4 no.3
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• pp.420-428
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• 1995

현재 사용하고 있는 액화천연가스 기화기는 관내부로 -162$^{\circ}C$의 액화가스가 흐르고, 관외부로 발전소 증기응축기 출구에서 배출된 20~3$0^{\circ}C$의 해수를 흐르도록 하여, 두 유체사이의 온도차로 기화시키는 간접접촉방식 열교환기가 사용되고 있다. 그러나 간접접촉방식 열교환기는 두 유체사이의 큰 온도차로 인한 금속재료의 피로현상과 해수의 염분에 의한 재질의 부식 및 미생물 부착 등의 원인으로 열전달효율이 저하되고 있다. 따라서 본 연구는 관을 중간매체로 하는 간접접촉식 열교환기대신 액화천연가스와 기화용수인 물을 직접접촉시키는 방법으로 이용하여, 위와 같은 문제점들을 근본적으로 해결하려 한다. 본 실험에서는 기화기내의 수위 500 mm와 물의 유량 10 l/min을 일정하게 고정시키고, 액화천연가스의 유량 0.12 ㅣ/min, 0.36 l/min, 0.6 l/min, 기화기내의 압력을 100 kPa, 300 kPa, 500kPa로 변화시키면서 기화기내의 기포, 온도분포, 급팽창현상, 동결현상 및 기화후 수분함유량등의 비등특성을 규명하였다. 실험결과 기화기내의 압력이 증가할수록 기포는 작고 균일한 분포를 이루고, 폭발적인 급팽창현상은 일어나지 않았다. 또한 동결현상은 액화천연가스의 기화를 방지하지 못하였으며, 기화된 천연가스내의 수분함유량 몰%는 압력과 유량이 증가함에 따라 감소하는 경향을 보이고 있다.

• Journal of the Korean Society of Safety
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• v.20 no.2 s.70
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• pp.38-43
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• 2005

Several nuclear power plants reported that they often found the combination cracks, which consist of longitudinal and circumferential cracks in the tubes. For the burst pressure of a tube with a single longitudinal or circumferential crack several experimental equations have been proposed in published literatures. But for the combination crack appropriate fracture criterion has not been proposed yet. In this study the burst pressures of a tube with a longitudinal crack or a T-type combination crack consisting of longitudinal and circumferential cracks were obtained experimentally and analytically. Fracture parameters such as crack opening angle (COA) were investigated by using elastic plastic analysis. Also the burst pressure far a T-type combination crack located near a tubesheet was considered to develop a length-based criterion. Because most of the axial, circumferential or combination cracks initiate in roll transition zone near the tubesheet.

• Corrosion Science and Technology
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• v.17 no.3
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• pp.116-122
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• 2018

The secondary coolant of a nuclear power plant has small amounts of various impurities (S, Pb, and Cl, etc.) introduced during the initial construction, maintenance, and normal operation. While the concentration of impurities in the feed water is very low, the flow of the cooling water is restricted, so impurities can accumulate on the Top of Tubesheet (TTS). This environment is chemically very complicated and has a very wide range of pH from acidic to alkaline. In this study, the characteristics of the oxide and the mechanism of stress corrosion cracking (SCC) are investigated for Alloy 690 TT in alkaline solution containing Pb, Cl, and S. Reverse U-bend (RUB) specimens were used to evaluate the SCC resistance. The test solution comprises 3m NaCl + 500ppm Pb + 0.31m $Na_2SO_4$ + 0.45m NaOH. Experimental results show that Alloy 690 TT of the crevice environment containing Pb, S, and Cl has significant cracks, indicating that Alloy 690 is vulnerable to stress corrosion cracking under this environment.

• Journal of Hydrogen and New Energy
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• v.19 no.6
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• pp.537-544
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• 2008

In this paper, flow characteristics of an adiabatic capillary tube in a transcritical $CO_2$ have been investigated employing the homogeneous model. The model is based on fundamental equations of mass, energy and momentum which are solved simultaneously. Two friction factors(Churchill) and viscosity(McAdams) are comparatively used to investigate the flow characteristics. Supercritical and subcritical thermodynamic and transport properties of $CO_2$ are calculated employing EES property code. Flow characteristics analysis of $CO_2$ adiabatic capillary tube is presented to offer the basic design data for the operating parameters. The operating parameters considered in this study include inlet temperature and pressure of an adiabatic capillary tube, evaporating temperature and inner diameter tube. The main results were summarized as follows : inlet temperature and pressure of an adiabatic capillary tube, evaporating temperature, mass flowrate and inner diameter of $CO_2$ adiabatic capillary tube have an effect on length of an adiabatic capillary tube.

• Journal of the Korean Institute of Gas
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• v.2 no.4
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• pp.1-6
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• 1998

In order to increase design efficiency, it is required to design steam boiler pressure parts systematically considering daily start-stop operation and load variation. The objective of this research is to develope an integrated system for increasing design efficiency of boiler pressure parts. The developed system consists of three program modules: (1) flexibility design module for the header stub considering fatigue life, (2) fatigue limit calculation and life evaluation module for the thick-walled boiler pressure part under cyclic operation using TRD301 code, (3) drawing automation module for the header and drum producing design drawings, welding data and bill of materials.

• Transactions of the Korean Society of Mechanical Engineers A
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• v.30 no.8 s.251
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• pp.993-1000
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• 2006

Operating experience of steam generators has shown that cracks of various morphology frequently occur in the steam generator tubes. These cracked tubes can stay in service if it is proved that the tubes have sufficient safety margin to preclude the risk of burst and leak. Therefore, integrity assessment using exact limit load solutions is very important for safe operation of the steam generators. This paper provides global and local limit load solutions for surface cracks in the steam generator tubes. Such solutions are developed based on three-dimensional (3-D) finite element analyses assuming elastic-perfectly plastic material behavior. For the crack location, both axial and circumferential surface cracks, and for each case, both external and internal cracks are considered. The resulting global and local limit load solutions are given in polynomial forms, and thus can be simply used in practical integrity assessment of the steam generator tubes.

• Proceedings of the Korean Society for Noise and Vibration Engineering Conference
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• 2008.04a
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• pp.630-636
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• 2008

1000MW급 증설과 관련하여 발전소 주변지역으로부터 민원이 제기된 3000MW급 화력발전소는 넓은 평지에 위치하여 발전소의 영향이 그대로 주변지역에 전달되는 상태임에도 일상 소음레벨이 환경 기준치를 만족하는 상태였으나 향후 증설에 따른 소음도 증가에 대비하여 소음영향을 예측하고 저감 대책을 검토하였다. 대형 화력발전소의 옥외소음원은 Booster fan, I.D.fan, 주변압기, 대형 철탑, 해수순환수 펌프 전동기, 증기방출관 등이 있다. 대상 주거지역의 경우는 대형팬에 의한 지향성이 크게 나타났다. 따라서, 발전소가 주변지역에 주는 소음별 기여도를 평가하고 영향이 큰 대형팬에 대한 대책으로써 기기주변에 방음벽을 설치하는 방안과 함께 소음원의 크기를 저감시킬 수 있는 소음기 대책을 추천하여 증설 예정호기를 비롯한 기존 호기중 주거지역에 영향이 큰 3000MW에 대하여 수립함으로써 소음저감 목표치를 달성하는 결과를 도출하였다.

• Journal of Institute of Control, Robotics and Systems
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• v.2 no.3
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• pp.236-241
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• 1996

This paper presents a new eddy current testing system for inspecting tubes of steam generator in nuclear power plant. The proposed system adopted embedded expert system concept to automate tasks of the inspection such as inspection planning and flaw signal interpretation, and integrated all the tasks into a client/server type computing architecture using database management system. Therefore, human factor errors occurred during inspection could be minimized and the inspection data could be transferred in real-time. As a result, we can increase the level of inspection confidence and the productivity of a personal inspector. A prototype of the proposed system has been developed for 5 years and the test operation has been performed in domestic nuclear power plants.

• Transactions of the Korean Society for Noise and Vibration Engineering
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• v.16 no.9 s.114
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• pp.904-911
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• 2006

A modified energy method for the fretting wear of the steam generator tube is proposed to calculate the wear-out depth between the nuclear steam generator tube and its support. Estimation of fretting-wear damage typically requires a non-linear dynamic analysis with the information of the gap velocity and the flow density around the tube. This analysis is very complex and time consuming. The basic concept of the energy method is that the volume wear rate due to the fretting-wear phenomena Is related to work rate which is time rate of the product of normal contact force and sliding distance. The wearing motion is due to dynamic interaction between vibrating tube and its support structure, such as tube support plate and anti-vibration bar. It can be assumed that the absorbed work rate would come from turbulent flow energy around the vibrating tube. This study also numerically obtains the wear-out depth with various wear topologies. A new dissection method is applied to the multi-span tubes to represent the vibrational mode. It turns out that both the secondary side density and the normal gap velocity are important parameters for the fretting-wear phenomena of the steam generator tube.

• 월간 기계설비
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• s.267
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• pp.65-71
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• 2012

지난 8월 13일 서울 종로구 소격동 국립현대미술관 서울관 공사현장에서 화재 발생으로 4명이 숨지고 18명이 중경상을 입는 등 많은 인명피해를 냈다. 이처럼 인명피해가 컸던 것은 우레탄 공사를 하던 밀폐공간에서 불이 나면서 발생한 유독가스 때문에 사람들이 제대로 대피하지 못했기 때문이다. 사고발생 원인으로 '용접공사' 여부를 놓고 공방을 벌였으나 경찰은 '전기합선'이라는 잠정 결론을 내렸다. 지난 2008년 1월에 발생한 경기도 이천 냉동창고 화재는 40명의 목숨을 앗아갔다. 화재 원인은 냉동배관을 설치하면서 전기 용접을 하기 위해 불을 붙였다가 공기 중에 차 있던 유증기(기름증기)와 만나면서 폭발이 일어난 것이었다. 인화성 액체(유기용제)를 취급하는 건설현장에서는 다량의 유증기가 발생할 수 있을 뿐만 아니라 건조한 조건일 경우 정전기에 의한 화재 폭발 누출사고의 발생 위험이 높다. 기계설비공사에서 화재, 폭발 위험성이 가장 큰 공사는 용접공사이기에 용접공사를 할 때 화재, 감전의 위험성을 배제한 후 공사에 들어간다. 용접으로 인한 사망사고의 유형으로는 용접 중 추락사고와 더불어 용접 불꽃이 가연성 물질에 옮겨 붙어 화재 발생으로 인한 질식사, 용접작업 중 절연체가 파손된 용접기 홀더 충전부의 접촉으로 인한 감전사 등이 있다. 본지는 용접으로 인한 화재 감전 등의 사고발생을 미연에 방지하기 위해 안전작업 수칙 및 안전수칙 체크리스트, 재해사례를 지난호부터 시리즈로 연재하고 있다.