• 대한기계학회논문집A
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• 제27권5호
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• pp.724-733
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• 2003

Fatigue design rules for welds in the ASME Boiler and Pressure Vessels Code are based on the use of Fatigue Strength Reduction Factors(FSRF) against a code specified fatigue design curve generated from smooth base metal specimens without the presence of welds. Similarly, stress intensification factors that are used in the ASME B3l.1 Piping Code are based on component S-N curves with a reference fatigue strength based on straight pipe girth welds. But the determination of either the FSRF or stress intensification factor requires extensive fatigue testing to take into account the stress concentration effects associated with various types of component geometry, weld configuration and loading conditions. As the fatigue behavior of welded joints is being better understood, it has been generally accepted that the difference in fatigue lives from one type of weld to another is dominated by the difference in stress concentration. However, general finite element procedures are currently not available for effective determination of such stress concentration effects. In this paper, a mesh-insensitive structural stress method is used to re-evaluate the S-N test data, and then more effective method is proposed for pressure vessel and piping fatigue design.

• 한국압력기기공학회 논문집
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• 제12권1호
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• pp.107-114
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• 2016

Four cylindrically shaped IHXs(Intermediate Heat Exchangers) are installed in the PHTS(Primary Heat Transfer System) of the PGSFR(Prototype Gen IV Sodium cooled Fast Reactor). As for the IHX, the temperature difference of structure is inevitable result caused by heat transfer between primary coolant sodium and IHTS(Intermediate Heat Transport System) sodium. It is necessary to evaluate the high temperature structural integrity of IHXs which operate at the elevated temperature condition over the creep temperature. In this paper, the high temperature structural integrity of IHX under assumed loading conditions has been reviewed according to ASME code.

• 한국압력기기공학회 논문집
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• 제5권2호
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• pp.35-39
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• 2009

In this study, Event Type Analysis System (ETAS) is developed for the accident evaluation in nuclear power plant. The ETAS system can be used in supporting regulator and/or operator under event situation in nuclear power plants. The ETAS system can categorize the all transient events to 3 categories such as Down-2000, Down-2173, and Slow Fluctuation. We develop the program structure for ETAS system and web-based ETAS system. The ETAS system will be used as sub module of Knowledge-Based Event Evaluation Network (K-EvENT) which is developing for the against the accident in nuclear power plants.

• KIEAE Journal
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• 제2권2호
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• pp.33-38
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• 2002

There are a number of practical uses for devices which are capable of piping large amounts of light: illumination of areas where there would be maintenance, safety, or security problems with electronic light sources; piping sunlight into indoor areas for illumination; and the conversion of high luminous efficacy, good color quality, high intensity discharge lamps into more acceptable linear of area sources of light. Prism light guides are hollow structures which pipe light by means of total internal reflectin(TIR). These devices are unique in their ability to combine the efficiency of TIR with the relatively low cost of hollow structure. An important application stems from their ability to transform a point source of light such as an incandescent or discharge lamp into a linear or area source of light or illumination. We report the development of an economical, flexible prismatic film for fabricating the light guide wall. This guide geometries and films are currently under development.

• 한국공작기계학회논문집
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• 제17권1호
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• pp.150-157
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• 2008

Bellows are commonly used in piping systems to absorb expansion and contraction in order to reduce stress. Unlike most piping components, bellows consist of a thin-walled shell of revolution with a corrugated meridian, in order to provide the flexibility needed to absorb mechanical movements. It is a composite shell structure consisting of at least one toroidal shell, an annular plate or conical shell. It is difficult to analyze the behavior of bellows because of its complex geometry. Simplified formulas for variable mechanical behaviors of bellows are provided by a standard called EJMA. An automatic design software for bellows is programming by using VBA(Visual Basic for Application) based on EJMA. Bellows engineers can effectively make a decision for bellows geometries because this software provides graphically design results in its post-processor. Bellows design software is expected to give quite a good guidance to practical design. The characteristics of bellows are also investigated through the automatic design process in bellows design software.

• 한국압력기기공학회 논문집
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• 제6권2호
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• pp.1-8
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• 2010

Nuclear steam generator tubes have experienced wear degradation at tube support structure. Morphology of wear scar was analyzed by using eddy current signal. A burst test facility for steam generator tubes was established and tubes with 3 types of defects were tested. The burst test results show that the depth of wear scar is the main factor influencing the burst pressure of tubes, meanwhile, both the longitudinal length and the angle also have effect on the burst pressure. Based on test results, the burst pressure equation for wear degradation was proposed.

• 한국압력기기공학회 논문집
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• 제19권2호
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• pp.171-178
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• 2023

For the phase boundary crack found in the gasket made of cast austenitic stainless steel in the nuclear power plant, the oxide layers were analyzed through SEM and TEM. The results showed that cracks initiated and propagated along the austenite/δ-ferrite phase boundary, the propagation path was changed to penetrate the inside of the phase. The oxide layer located at the periphery of the crack along the phase boundary was identified as a complex multi-layered spinel structure, and Cr-rich carbides were also detected in the oxide. The cracks that propagated inside the austenite matrix were attributed to the presence of high external stresses and impurities.

• 대한토목학회논문집
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• 제37권5호
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• pp.787-799
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• 2017

저수지 제체 내 수로 구조물과 흙 접촉면의 장기적인 누수가 제체 파괴의 주원인 중의 하나 임에도 불구하고 이에 대한 연구는 미미한 실정이다. 배수통관과 같은 구조물이 부분 파손되어 누수가 발생하는 경우 외형적으로 관측하기 곤란하고 파이핑 등에 의한 제체 손상 우려가 있어 이에 대한 연구가 필요하다. 본 연구는 저수지 제체를 관통하는 배수 통관이 부등침하 등으로 인해 통관 일부가 파손되어 누수가 발생하는 경우 저수지의 제체 형태를 코어형 단면과 균일형 단면으로 구분하여 수위변화에 따른 2차원 침투해석을 수행하였다. 연구결과 저수지 등의 제체를 관통하는 배수 통관으로의 누수가 발생 할 경우 통관 하부보다는 상부가 파손되어 누수가 되는 경우가 파이핑 발생 가능성이 크며, 특히 제체 하류측에서 누수가 발생하는 경우 제체 중심 코어부의 존재는 제체 안정 유지에 도움을 주고 있다고 판단된다. 또한 저수지 제체 내부 간극수압의 급격한 감소가 관측되면 파이핑 발생 우려에 대한 심도 있는 고려가 필요할 것으로 사료된다.

• 한국지진공학회논문집
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• 제15권3호
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• pp.37-43
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• 2011

구조물 내 설치된 파이프시스템은 주로 내부구성원들의 인간생활에 근간이 되는 기반시설로서 현대 도시생활의 생명선과 같은 역할을 한다. 이들 구조물 내 파이프시스템이 만약 지진발생에 의하여 손상될 경우 1차적으로 구조물 내 기능성이 저하되고 구조물 내 많은 정신적, 물질적 피해가 발생할 수 있다. 실제 내진공학에서 지진발생에 따른 비구조재요소의 거동은 크게 중요하게 고려되지 않으나 인적 및 물적 피해와 매우 밀접하게 연관되는 가스 혹은 수계파이프시스템에 대한 비구조적 요소의 거동예측 및 성능평가 연구는 보다 효과적인 구조물 유지관리를 위하여 그 필요성이 크다고 판단된다. 본 연구는 현재 일반적으로 널리 시공되어져 있는 노후 철근콘크리트 빌딩구조물 내 설치된 가스 혹은 수계파이프시스템에 대하여 실제 지진발생이 예측되는 거동을 살펴보고 이들 거동에 따른 성능평가 및 현 설계기준에 대한 검토도 병행하여 수행하고자 한다. 이를 위하여 본 연구에서는 해석적으로 발생 가능한 총 10회의 지진파에 대하여 현재 실제 건물 내 기설치된 수계파이프시스템 모델링 및 해석을 통하여 그 결과를 검증, 평가하였으며 부가적으로 실제 발생 가능한 파괴유형 분석을 통하여 현 설치된 수계파이프시스템의 설계에 대한 적절한 내진보강방법에 대하여도 제안하고자 한다.

• Nuclear Engineering and Technology
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• 제41권10호
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• pp.1323-1332
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• 2009

The IHX (Intermediate Heat eXchanger) for a pool-type SFR (Sodium-cooled Fast Reactor) system transfers heat from the primary high temperature sodium to the intermediate cold temperature sodium. The upper structure of the IHX is a coaxial structure designed to form a flow path for both the secondary high temperature and low temperature sodium. The coaxial structure of the IHX consists of a central downcomer and riser for the incoming and outgoing intermediate sodium, respectively. The IHX of a pool-type SFR is supported at the upper surface of the reactor head with an IHX support structure that connects the IHX riser cylinder to the reactor head. The reactor head is generally maintained at the low temperature regime, but the riser cylinder is exposed in the elevated temperature region. The resultant complicated temperature distribution of the co-axial structure including the IHX support structure may induce a severe thermal stress distribution. In this study, the structural feasibility of the current upper support structure concept is investigated through a preliminary stress analysis and an alternative design concept to accommodate the IHTS (Intermediate Heat Transport System) piping expansion loads and severe thermal stress is proposed. Through the structural analysis it is found that the alternative design concept is effective in reducing the thermal stress and acquiring structural integrity.