• Journal of the Korean Society for Nondestructive Testing
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• v.13 no.4
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• pp.42-46
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• 1994

원자력발전소(原子力發電所)의 방진기의 역할은 운전중(運轉中) 지진(地震)이나 혹은 수격작용(水擊作用)등 순간적인 동적 하중의 발생으로부터 관련 배관(配管)과 기기(機器)를 보호하는 것이다. 1989년 이후 ASME Sec. XI에서 50kips 이상의 대형 방진기도 ASME/ANSI OM Part 4에 따라 육안검사(肉眼檢査) 및 성능시험(性能試驗)을 할 것을 추가 요구하고 있다. 따라서 본 보고서는 방진기(防震機) 기능, 미국 원전 방진기의 손상 사례, 검사(檢査) 기술기준(技術基準) 및 요구사항(要求事項)을 검토(檢討)하여 검사 및 성능시험을 적절한 제반 기술기준에 의거 수행토록 하며, 수행 결과 수반되는 손상 방진기에 대한 원인규명(原因糾明)과 까다로운 후속조치(後續措置)의 실시로 원전 40여년 수명기간동안 배관계통(配管系統) 및 기기(機器)의 건전성을 확보하는데 기여코자 한다.

• Journal of the Korean Institute of Gas
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• v.2 no.2
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• pp.18-25
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• 1998

According to the requirements of ANSI B3l.8, the pipe thickness is determined with hoop stress resulted from internal pressure. And the other loads induced by soil, vehicle, thermal expansion, ground subsidence, etc shall be evaluated rationally. There are two ways of calculating stress of buried gas pipeline. The first is FEM. FEM can calculate the stress regardless of the complexity of pipeline shape and boundary conditions. But it needs high cost and long time. The second is the way to use equation. The reliable equations to calculate the stress of buried gas pipeline was developed and have been used in designing pipeline and evaluating pipeline safety, But these equation are very difficult to understand and use for non-specialist. For easy calculation of non-specialist, the new computer program to calculate stress of buried natural gas pipeline have been developed. The stress is calculated by the equations and extrapolation of the graph resulted from FEM. The full paper is consist of series I and II. In this paper, series I, the calculating equation of the program is explained in detail.

• Journal of the Korean Institute of Gas
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• v.2 no.2
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• pp.26-33
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• 1998

The thickness of buried gas pipeline is determined mainly with internal pressure and location factor according to the requirements of ANSI B3l.8. But the stress of buried gas pipeline is determined by not only internal stress but also external loads. The change of burying and environmental conditions, therefore, may result in increasing stress of pipeline. In order to avoid the decrease of safety degree resulting from change of environmental condition, the evaluation of stress level shall be necessary. The reliable equations have been developed for calculating stress of buried pipeline from internal pressure, earth load, vehicle load, ground subsidence. But they are very difficult to understand and use for non-specialist. For easy calculation of non-specialist, the new computer program to calculate stress of buried natural gas pipeline have been developed. The program can calculate maximum stress resulted from earth load, vehicle load, thermal load, four type ground subsidence. The stress is calculated by the equations and extrapolation of the graph resulted from FEM. In this paper, as the series of paper I, the operating method and the functions of the program is explained.

• Journal of the Korean Society for Nondestructive Testing
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• v.30 no.4
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• pp.380-385
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• 2010

The integrity of components and piping of operating nuclear power plants has been identified by in-service inspection(ISI) requirements and activities commensurate with standards and codes such as KEPIC MI or ASME Code Section XI. However, the other various degradation mechanisms not considered during design stage of nuclear power plants have been checked by enhanced ISI. The requirements of enhanced ISI have been voluntarily developed by the industry itself or strickly issued by regulatory body. Even though the requirements were developed by the industry, they should be reviewed by regulatory body for their application in nuclear power plants. The enhanced ISI activities and requirements of non-destructive examination(NDE) which reflect the degradation issues in nuclear power industry will be primarily discussed in this paper.

• Transactions of the Korean Society of Pressure Vessels and Piping
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• v.7 no.3
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• pp.40-47
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• 2011

KSNPs(Korea Standard Nuclear Power Plant) have been applied the break exclusion criteria to the high energy lines passing through containment penetration area to ensure that piping failures would not cause the loss of containment isolation function, and to reduce the resulting dynamic effects. Systems with the criteria are the Main Steam system, Feed Water system, Steam Generator Blowdown system, and Chemical & Volume Control system. In accordance with FSAR(Final Safety Analysis Report), a 100% volumetric examination by augmented in-service inspection of all pipe welds appled the break exclusion criteria is required for the break exclusion application piping. However, it is difficult to fully satisfy the requirements of inspection because 12", 8" and 6" weldolet weldments of Main Steam pipe line have complex structural shapes. To resolve the difficulty on the application of conventional UT(Ultrasonic Testing) technique, realistic mock-ups and UT calibration blocks were made. Simulations of conventional UT were performed utilizing CIVA, a commercial NDE(Nondestructive Examination) simulation software. Phased array UT experiments were performed through mock-up including artificial notch type flaws. A phased array UT technique is finally developed to improve the reliability of ultrasonic test at main steam line pipe to 12", 8" and 6" branch connection weld.

• Transactions of the Korean Society of Mechanical Engineers A
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• v.36 no.9
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• pp.1103-1108
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• 2012

A main steam pipe system is a branch pipe that connects a boiler with a turbine. Water hammering analysis is very important for limiting the damage caused to pipe systems by operation conditions. Water hammering created by an unsteady flow in pipeline systems can cause excessive change in pressure, vibration, and noise. The main steam pipe structure should be designed to safely maintain the pressure pulsation and several vibrations under operation environments. This study evaluated the structural integrity of a main steam pipe during suspended and normal operation by using the ASME fatigue life methodology and finite element analysis. In the analysis, water hammering was used for transient analysis. The calculated alternating stress and fatigue stress were compared with the applicable limits of ASME fatigue life. All the evaluation results satisfied the requirements of the ASME fatigue life.

• Proceedings of the Korean Reliability Society Conference
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• 2001.06a
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• pp.245-255
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• 2001

원전 가동전/가동중검사 결과의 신뢰도(reliability)는 원전 배관기기의 건전성에 직결되는 것으로써 결함 발견 시 적용되는 파괴역학해석(FMA)은 비파괴검사 결과에 대한 100%의 신뢰를 전제하고 있다. 그러나 비파괴검사가 어느 정도 신뢰성을 가지고 있는지에 대한 평가가 국내에서는 거의 수행된 바가 없었다. 따라서, 본 연구에서는 원전의 비파괴검사 규제 요건의 기술적 근거를 확보하고, 원전 기기 건전성 평가 및 안전성 향상을 위한 합리적 규제지침을 수립하기 위하여 국내 원전 가동중검사(ISI)에 적용되거나 일반 산업계에 적용되고 있는 초음파탐상검사에 대하여 기량검증 Round Robin Test에 의한 통계적 신뢰도를 평가하고자 한다. 이를 위해 초음파검사 PD-RRT 결과의 통계적 신뢰도 평가 모델을 고찰하고, 결함검출성능 평가, 결함크기 측정 평가, 팀 오차 분석 등 초음파검사 PD-RRT 결과의 통계적 신뢰도를 평가하였다.

• Proceedings of the Korean Nuclear Society Conference
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• 1996.05b
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• pp.55-60
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• 1996

원자력발전소 운전시 원자로냉각재는 부식 방지를 위해 적절한 화학물질을 함유하고 있어야한다. 이러한 원자로냉각재의 수질화학 조절은 유량조절 기능과 화학제주입 기능을 가진 화학 및 체적제어계통의 화학제주입탱크 및 체적제어탱크에 의하여 이루어진다. 본 연구에서는 영광5,6호기에서 화학제주입계통의 연결위치를 충전펌프 후단에서 전단으로 변경하고, 원자로보충수펌프에 의하여 화학제주입을 수행할 경우 요구되는 주입운전시간 특성에 대해 수치해석을 이용하여 분석하였다. 분석은 설계요건에서 요구되는 화학제주입탱크의 용량 및 주입유량을 고정하고 탱크의 구조적형상 변경, disk block 설치 및 주입속도를 변경(입구배관 크기 변경)하여 각각의 경우에 대하여 시간변화에 대한 탱크 내에서의 유속분포, 농도분포, 평균농도 등 을 구하였다. 분석결과 발전소의 빠른 화학제주입운전을 위해서는 탱크 내에 혼합효과를 중대 시킬 수 있는 disk block의 설치가 요구됨을 알 수 있었다.

• Proceedings of the Korean Nuclear Society Conference
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• 1997.05a
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• pp.534-541
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• 1997

1000MWe급 피동형원자로기 안전계통 성능 및 RELAP5 코드의 적용성 평가를 목적으로 AP600을 참조노형으로 설정된 1000MWe급 대용량 피동형원자로에 대한 냉각재 상실사고를 모의 해석하였다. 대형냉각재상실사고시 발생되는 현상들은 기존 원자로와 큰 차이가 없고, 이들 현상을 모의하기 위한 모델링 요건들이 피동형계통 분석에 동일하게 요구되었으며, 계산된 PCT가 규제기관의 허용치에 충분한 여유도를 갖고 있어 대형냉각재상실사고시 충분한 노심냉각 능력을 갖는 것으로 평가되었다. 또한 안전주입 배관이 파단되는 소형냉각재 상실사고를 해석한 결과 KP1000의 피동안전계통은 ADS의 작동에 의하여 노심을 노출시키지 않고 적절한 사고완화 기능을 수행할 수 있는 것으로 분석되었다.

• Journal of the Korean Society for Nondestructive Testing
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• v.33 no.4
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• pp.368-375
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• 2013

Failure of small bore piping welds is a recurring problem at nuclear power plants. And the socket weld cracking in small bore piping has caused unplanned plant shutdowns for repair and high economic impact on the plants. Consequently, early crack detection, including the detection of manufacturing defects, is of the utmost importance. Until now, the surface inspection methods has been applied according to ASME Section XI requirements. But the ultrasonic inspection as a volumetric method is also applying to enforce the inspection requirement. However, the conventional manual ultrasonic inspection techniques are used to detect service induced fatigue cracks. And there was uncertainty on manual ultrasonic inspection because of limited access to the welds and difficulties with contact between the ultrasonic probe and the OD(outer diameter) surface of small bore piping. In this study, phased array ultrasonic inspection technique is applied to increase inspection speed and reliability. To achieve this object, the 3.5 MHz phased array ultrasonic transducer are designed and fabricated. The manually encoded scanner was also developed to enhance contact conditions and maintain constant signal quality. Additionally inspection system is configured and inspection procedure is developed.