• 제목/요약/키워드: Piping Material

검색결과 223건 처리시간 0.021초

부자식 유량계의 성능특성에 관한 연구 (A Study on the Performance Characteristics of Float Type Flow Meter)

  • 김춘식;김경근;이영호
    • Journal of Advanced Marine Engineering and Technology
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    • 제9권4호
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    • pp.339-347
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    • 1985
  • Precise measurement of flowrate is considered as an important measuring factor in mechanical and chemical experiment. Although there are many methods to measure flowrate, Float type flowmeter is widely used because of its easy attachment to piping and high measuring precision. To design the precise float type flowmeter, much design information such as tapered-tube dimensions, float size, float shape and float material is required. In this paper, fundamental design theory for float type flowmeter according to the given flowrate range is suggested and compensation coefficients of volumetric and weight flowrate for water, R-113 and air are calculated.

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유동가속부식에 대한 통계적 모델링 해석방법 개발: 유속, 온도, pH 및 Cr 함량의 효과 (Development of Statistical Modeling Methodology for Flow Accelerated Corrosion: Effect of Flow Rate, Water Temperature, pH, and Cr Content)

  • 이경근;이은희;김성우;김동진
    • 한국압력기기공학회 논문집
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    • 제12권2호
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    • pp.40-49
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    • 2016
  • Flow accelerated corrosion (FAC) of the carbon steel piping has been a significant problem in nuclear power plants. FAC occurs under certain hydrodynamic, environmental, and material conditions, and extensive research into the factors of FAC has been conducted. The basic process of FAC is now relatively well understood; however, a full mechanistic model has not yet been established. Recently, the Korea Atomic Energy Research Institute (KAERI) has built a large experiment loop system for FAC. To produce significant experimental results using this system, the factors affecting on FAC should be analyzed quantitatively, and a model needs to be developed. In this work, a statistical modeling methodology to develop an empirical model is described in detail, and a preliminary model is suggested. Firstly, FAC data were collected from the research literature in Japan and the results of domestic experiments. The flow rate, water temperature, pH at room temperature, and the Cr content are selected as major factors, and nonlinear regression is used to find the best fit of the available data. An iterative procedure between suggesting and evaluating a model is used until an optimum model is obtained. The developed model gives the FAC rate comparable to the measured FAC rate. The developed model is going to be refined using additional laboratory data in the future.

수계소화설비용 경량벽 스테인리스 강관의 사용가능성 평가에 관한 연구 (A Study on the Possibility of using Light-Wall Stainless Steel Pipe for Water-Based Fire Protection System)

  • 남준석;원성연;김영호;민경탁;박승민
    • 한국화재소방학회논문지
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    • 제24권5호
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    • pp.94-101
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    • 2010
  • 수계소화설비에 사용되고 있는 관으로는 배관용 탄소강관, 압력배관용 탄소강관, 동관 등이 사용되고 있다. 최근 건축물의 고층화, 복합화로 소화설비에는 내식성이 우수하고, 시공성이 간편하며, 가볍고 경제적인 관의 사용이 고려되고 있다. 이러한 특징을 가진 스테인리스 강관과 기존에 사용되고 있는 동관의 물성, 강도, 내식성, 내열성 등의 비교를 통해 스테인리스 강관의 소화설비로의 사용 가능성을 평가하고자 하였다. 그 평가결과로 경량벽 스테인리스 강관인 일반배관용 스테인리스 강관(KS D 3595)은 1.2MPa미만의 압력에서 수계소화설비에 사용될 수 있는 충분한 물성, 강도, 내식성, 내열성 등을 가지고 있음을 확인할 수 있었다.

하천제방의 건전도 평가를 위한 수치해석적 연구 (Numerical Analysis for Integrity Evaluation of River Bank)

  • 장혁상;변오셉;천병식;최봉혁;김진만
    • 한국지반환경공학회 논문집
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    • 제11권11호
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    • pp.19-26
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    • 2010
  • 하천제방 건전도 평가에 대한 영향인자는 누수의 경우 제체, 기초를 구성하는 지반의 투수계수가 있으며, 제방의 높이, 둑마루 폭 등 기하학적 요인이 있고, 비탈면 안정성의 경우 제체 및 기초 지반의 재료적 특성, 제체 비탈면의 형상, 강우나 하천수의 침투에 따른 영향 등이 있다. 본 연구에서는 하천제방 침투해석에 중요한 투수계수 변화에 따른 영향 검토를 위하여 기존 설계결과 타당성 검토, 문헌자료 투수계수 사용에 따른 안정성 평가, 기초지반 투수계수변화에 따른 안정성 검토를 수행하였다. 영향인자 평가 결과, 설계 시 사용되는 투수계수는 동일한 토질에 대해서도 설계문헌에 따라 상이한 것으로 나타났으며, 검토 결과 파이핑 안전율에 큰 영향을 미치는 것으로 평가되었다.

Crack growth analysis and remaining life prediction of dissimilar metal pipe weld joint with circumferential crack under cyclic loading

  • Murthy, A. Ramachandra;Gandhi, P.;Vishnuvardhan, S.;Sudharshan, G.
    • Nuclear Engineering and Technology
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    • 제52권12호
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    • pp.2949-2957
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    • 2020
  • Fatigue crack growth model has been developed for dissimilar metal weld joints of a piping component under cyclic loading, where in the crack is located at the center of the weld in the circumferential direction. The fracture parameter, Stress Intensity Factor (SIF) has been computed by using principle of superposition as KH + KM. KH is evaluated by assuming that, the complete specimen is made of the material containing the notch location. In second stage, the stress field ahead of the crack tip, accounting for the strength mismatch, the applied load and geometry has been characterized to evaluate SIF (KM). For each incremental crack depth, stress field ahead of the crack tip has been quantified by using J-integral (elastic), mismatch ratio, plastic interaction factor and stress parallel to the crack surface. The associated constants for evaluation of KM have been computed by using the quantified stress field with respect to the distance from the crack tip. Net SIF (KH + KM) computed, has been used for the crack growth analysis and remaining life prediction by Paris crack growth model. To validate the model, SIF and remaining life has been predicted for a pipe made up of (i) SA312 Type 304LN austenitic stainless steel and SA508 Gr. 3 Cl. 1. Low alloy carbon steel (ii) welded SA312 Type 304LN austenitic stainless-steel pipe. From the studies, it is observed that the model could predict the remaining life of DMWJ piping components with a maximum difference of 15% compared to experimental observations.

SG365강의 파괴저항특성과 찢어짐계수에 관한 연구 (A Study on the J-Resistance Characteristics and Material Tearing Modulus of SG365 steel)

  • 임만배;윤한기
    • 한국해양공학회지
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    • 제15권3호
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    • pp.75-80
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    • 2001
  • The elastic plastic fracture toughness of this material is evaluated by the an unloading compliance method according to the ASTM E813-97 and E1152-97 method on the smooth and side groove 1CT specimens. The effect of smooth and side groove is studied on the material tearing modulus and characterizes the crack tip field under the plane stress and strain. SG-365 steel is observed that J-R curve and Tmat value decrease as 0%, 20%, 30%, and 40%. The 40% side grooved specimen is very useful in estimation of the $J_IC$. Because it is much easier than the smooth specimen to the onset of the ductile tearing by the R curve method. Besides. it improves the accuracy of toughness values, decreases the scattering the them and tunneling and shear lip by the side groove. Applicability of tearing modulus($T_J$ proposed by paris et al as instability panameter for this material is investigated.

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선박용 벨로우즈의 형상최적화에 관한 연구 (A study on the shape optimization of ship's bellows)

  • 김종필;김현수;김형준;조우석;제승봉
    • 한국정밀공학회:학술대회논문집
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    • 한국정밀공학회 2005년도 춘계학술대회 논문집
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    • pp.1303-1306
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    • 2005
  • The mechanical properties of bellows, such as the extensibility and the strength can be changed depending on the shape. For the shipbuilding material, it is favorable that the fatigue life is long due to the elastic property and the reduction of thermal stress in piping system. Nowadays, the domestic production and design of bellows are based on the E.J.M.A Code. Therefore, the design standard is in need because of much errors and lack of detailed analysis. In this study, it is attempted to find out the optimal shape of U-type bellows using the finite element method. The effective factors, mountain height, length, thickness, and number of mountains and the length of joint are considered and the proper values are chosen for the simulation. The results shows that if the number of mountains are reduced, the volume decreases while the stress increases. However, the number of mountains are increased, the volume increases above the standard volume and the stress obviously increases. In addition, the effect of the thickness of bellows on the stress is very large. Both of the volume and stress are decreasing at a certain lower value region.

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Applicability of Existing Fracture Initiation Models to Modern Line Pipe Steels

  • Shim, Do Jun
    • 한국압력기기공학회 논문집
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    • 제12권2호
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    • pp.1-24
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    • 2016
  • The original fracture criteria developed by Maxey/Kiefner for axial through-wall and surface-cracked pipes have worked well for many industries for a large variety of relatively low strength and toughness materials. However, newer line pipe steels have some unusual characteristics that differ from these older materials. One example is a test data that has demonstrated that X80 line-pipe with an axial through-wall-crack can fail at pressures about 30 percent lower than predicted with commonly used analysis methods for older steels. Thus, it is essential to review the currently available models and investigate the applicability of these models to newer high-strength line pipe materials. In this paper, the available models for predicting the failure behavior of axial-cracked pipes (through-wall-cracked and external surface-cracked pipes) were reviewed. Furthermore, the applicability of these models to high-strength steel pipes was investigated by analyzing limited full-scale pipe fracture initiation test results. Based on the analyzed results, the shortcomings of the available models were identified. For both through-wall and surface cracks, the major shortcomings were related to the characterization of the material toughness, which generally leads to non-conservative predictions in the J-T analyses. The findings in this paper may be limited to the test data that were consider for this study. The requisite characteristics of a potential model were also identified in the present paper.

원자로 내부구조물 재료열화이력 및 관리방안 (Material degradation and its management of reactor internals in PWR)

  • 황성식;김성우;김동진;최민재;임연수
    • 한국압력기기공학회 논문집
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    • 제12권1호
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    • pp.1-10
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    • 2016
  • The number of nuclear power plants operating in Korea was 24 as of year 2015. Nine units out of 24 units have been operated for a period over 20 years. Kori unit 1 has been in operation for 40 years, and an extended operation for Wolsong unit 1 was decided in 2015. There has been reported some crackings in reactor internals in PWR have been reported in Europe, USA, Japan and Korea, and some of them were replaced with new one. Repair and replacement technologies for the reactor internals have been developing in order to meet the regulatory requirements for long term operation in Korea. The technologies will also be used for the exported nuclear units. It is required to review degradation history of the reactor internals worldwide as a part of the degradation management program development. Schematics of reactor internals designed and supplied by Westinghouse, Framatome and Combustion Engineering are described herein. Materials degradation history of reactor internals of PWR plants in USA, Japan and Europe is surveyed and summarized. Some events from Korean plants are also described. Aging management strategy for the internals is suggested.

소듐냉각고속로(원형로) 주요기기 제작 특성 (Manufacturing characteristic of major components for prototype SFR)

  • 최한광;이중곤;전일정;김세훈;이정규;김용수;김철;안동현
    • 한국압력기기공학회 논문집
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    • 제12권1호
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    • pp.115-125
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    • 2016
  • The prototype SFR has currently been under design by KAERI. The size of its major components is much larger than that of APR1400 and high temperature materials are applied for it. The increased size of components and those specific materials effect on material procurement, manufacturing process and fabrication facilities. The manufacturing methods are studied for Reactor Vessel/Guard Vessel, Control Rod Drive Mechanism, Heat Exchanger, Primary Pump, Reactor Vessel Internals, Steam Generator and In-Vessel Transfer Machine. The proper manufacturing methods are suggested for each component including side forging technology for ultra large forgings of Reactor Vessel to minimize the weld seams on which In-service Inspection should be conducted.