• Title/Summary/Keyword: 기계적 건전성

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조합소식

  • 대한기계설비건설협회
    • 월간 기계설비
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    • 통권287호
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    • pp.50-53
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    • 2014
  • 올해 3월 대한설비건설공제조합 총회에서 김기석 신임 이사장이 선임됐다. 국토교통인력개발원장을 역임한 인사(人士)로, 취임과 동시에 업계의 많은 관심을 받고 있는 김 신임 이사장은 조합원사의 발전과 조합의 도약을 위해 일하겠다고 취임 일성을 밝혔다. 이를 위해 김 이사장은 앞으로 조합원에 대한 금융지원 확대와 조합 재무건전성 강화라는 조합의 기본 역할에 충실하는 한편, 조합원사와 적극적으로 소통하고 상생하기 위한 활동을 더욱 강화해 나갈 계획이다. 본지는 김기석 이사장을 만나보았다.

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A Comparative Study on the Applicability of CNT-coated Glass Fiber for Wind Blades (풍력 블레이드를 위한 CNT 코팅 유리섬유의 적용성에 대한 비교 연구)

  • Jang, Hong-Kyu;Kim, Young-Chul
    • Composites Research
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    • 제29권6호
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    • pp.336-341
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    • 2016
  • This paper conducted the study on the electromagnetic and mechanical applicability of CNT-coated glass fiber for wind blades. Large-size wind blade has the serious pending problems to meet the target, such as interfering radar signals, increasing weights, and increasing repair costs. In this paper, we are suggesting the CNT-coated glass fiber in order to overcome these problems. First, the CNTs were strongly coated on the surfaces of glass fiber by suggested coating process, and the CNT-coated glass fiber/epoxy composites were fabricated by Va-RTM process. We designed and fabricated a radar absorbing structure using the CNT-coated glass fiber, which showed over 90% radar absorbing performance between 8.3 and 12.1 GHz frequency. In addition, we confirmed the improvement of mechanical properties on the strength and modulus of tensile, compressive, and in-plane shear.

A Study for Experiment to Measure Mechanical Properties of Pressurizer Nozzle and Safety-Ends in Nuclear Power Plant (원전 가압기 노즐 및 안전단 재료에 대한 기계적 물성시험 연구)

  • Lee, Kyoung-Soo;Lee, Sung-Ho;Kim, Jin-Weon
    • Journal of the Korean Society for Nondestructive Testing
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    • 제33권2호
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    • pp.147-153
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    • 2013
  • Recently the primary water stress corrosion cracking(PWSCC) has occurred in the dissimilar metal weld region between pressurizer nozzle and safe-end in nuclear power plants(NPPs). As material of the pressurizer nozzle, SA508 Gr. 3 low alloy steel was used. F316L stainless steel and Alloy 82/182 were used as safe-end and weld metal, respectively. Although mechanical properties are needed for evaluation of the structural integrity against flaw in the material, material specification and standard don't supply those properties. Therefore, the present study conducted tensile and fracture toughness tests on SA508 Gr.3 and F316L stainless steel at ambient temperature and operating temperature of NPPs and reported the tested results.

The Estimation of Neutron Fluence in Nuclear Reactor Vessel Materials by the Analysis of Ultrasonic Characteristics (초음파특성 분석에 의한 원자로 재료의 중성자 조사량 예측)

  • Lee, Sam-Lai;Chang, Kee-Ok;Kim, Byoung-Chul
    • Journal of the Korean Society for Nondestructive Testing
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    • 제21권3호
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    • pp.307-312
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    • 2001
  • Ultrasonic signals from Charpy impact test specimen have been analyzed in order to evaluate the integrity of reactor pressure vessel. Base and weld metal that were extracted from reactor vessel doting plant outages according to the schedule of the surveillance test required by the related regulations have been used and the ultrasonic test parameters including velocity, attenuation, etc. showed a close correlations with the amount of neutron irradiation for base metal, relatively homogeneous materials. This result showed certain possibility where a nondestructive method could be used to predict the fluence of the Irradiation due to neutron in nuclear reactor vessel materials.

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Structural Integrity Assessment of High-Strength Anchor Bolt in Nuclear Power Plant based on Fracture Mechanics Concept (원자력발전소 고강도 앵커 볼트의 파괴역학적 건전성평가)

  • Lim, Eun-Mo;Huh, Nam-Su;Shim, Hee-Jin;Oh, Chang-Kyun;Kim, Hyun-Su
    • Transactions of the Korean Society of Mechanical Engineers A
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    • 제37권7호
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    • pp.875-881
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    • 2013
  • The failure of a bolted joint owing to stress corrosion cracking (SCC) has been considered one of the most important structural integrity issues in a nuclear power plant. In this study, the failure possibility of bolting, which is used to support the steam generator of a pressurized water reactor, owing to SCC and brittle fracture was evaluated in accordance with guidelines proposed by the Electric Power Research Institute, which are called the Reference Flaw Factor method. For this evaluation, first, detailed finite element stress analyses were conducted to obtain the actual nominal stresses of bolting in which either service loads or bolt preloads were considered. Based on these nominal stresses, the structural integrity of bolting was addressed from the viewpoints of SCC and toughness. In addition, the accuracy of the EPRI Reference Flaw Factor for assessing bolting failure was investigated using finite element fracture mechanics analyses.

Design and Integrity Evaluation of High-temperature Piping Systems in the STELLA-2 Sodium Test Facility (STELLA-2 소듐 시험 시설 고온 배관 계통의 설계 및 건전성 평가)

  • Son, Seok-Kwon;Lee, Hyeong-Yeon;Ju, Yong-Sun;Eoh, JaeHyuk;Kim, Jong-Bum;Jeong, Ji-Young
    • Transactions of the Korean Society of Mechanical Engineers A
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    • 제40권9호
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    • pp.775-782
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    • 2016
  • In this study, elevated temperature design and integrity evaluation have been conducted using two different piping design codes for the high-temperature piping systems of sodium integral effect test loop for safety simulation and assessment(STELLA-2) being developed by KAERI(Korea Atomic Energy Research Institute). The design code of ASME B31.1 for power piping and French nuclear grade piping design guideline, RCC-MRx RD-3600 were applied, and conservatism of those codes was quantified based on the piping integrity evaluation results. The piping system of Model DHRS, Model IHTS and PSLS are to be installed in STELLA-2. The integrity evaluation results for the three piping systems according to the two design codes showed that integrity of the piping system was confirmed. As a code comparison result, ASME B31.1 was shown to be more conservative for sustained loads while RD-3600 was more conservative for thermal loads compared to B31.1.

원자력分野에서의 破壞力學 現況 -법적 요구사항을 중심으로 (II)-

  • 송달호;손갑헌
    • Journal of the KSME
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    • 제20권6호
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    • pp.457-467
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    • 1980
  • 가동중조사(ISI)에 적용되는 ASME-MI 의 1974년 Edition에 ISI시 검출된 흠함을 평가하는 절 차가 제시되었다는 것은 이미 언급한 바 있다. 가동중검사의 개념은 ASME-III에 따라 건설된 부품이라 하더라도 원자력발전소의 온 수명기간동안 또는 정해진 수명기간동안 재료 내부에 흠 함이 전혀 생기지 않는다거나 또는 성장하지 않는다고 볼 수 없다는데 에 근거를 둔 것이다. 즉, 부품을 건설할 때 ASME-III의 규정에 따라 수행한 비파괴시험(nondestructive examination)에 의하여 합격된 부품이라 할지라도 시험방법의 유효성 및 합격기준등에 의하여 발견되지 않았 거나, 발견되었더라도 합격된 흠합등이 있을 수 있다. 이러한 흠함들이 원자로의 가동과 더불어 성장하거나, 또는 부품의 사용조건에 따라 흠함이 새로이 발생할 경우는 RCPB의 구조적 건전성 및 안정성은 위협을 받게된다. 이에 대처하기 위하여 원자력발전소의 전수명기간의 통하여 정 기적으로 ISI를 수행해 줄 것이 10CFR50의 50, 55a, "Codes and Standards"에 법적으로 명문 화되어 있다. ISI 시발견된 흠함은 그 크기를 평가하여 합격기준을 초과하는 경우에는, 흠함의 제거(removal), 항리(repair), 부품의 대체(replacement), 또는 파괴력학적인 해석에 의하여 그러한 흠함이 구조건 안전성을 손상시키지 않는다는 것을 입증해 주어야 한다. ISI 시에 검출된 흠함을 평가하고 파괴력학적으로 해석하는 규정으로서 ASME-XI에 명시된 절차는 다음과 같다.차는 다음과 같다.

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A Study on the Structural Integrity Considering the Installation of a Micro-tube Heat Exchanger (미세튜브 열교환기의 장착을 고려한 구조건전성에 관한 연구)

  • Oh, Se Yun;Kim, Tae Jin;Cho, Jong Rae;Jeong, Ho Sung
    • Transactions of the Korean Society of Mechanical Engineers A
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    • 제39권4호
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    • pp.447-451
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    • 2015
  • The objective of this study is to predict the structural characteristics of a heat exchanger mounted on an aircraft engine using finite element analysis. The plastic fracture and life of the heat exchanger were estimated by a thermo-mechanical analysis. Tensile tests were conducted under high temperature conditions (700, 800, 900, 1000 K) using five specimens to obtain the mechanical properties of the Inconel 625 tubes. To assess the structural characteristics of the heat exchanger, the full and partial models were applied under the operating conditions given by the thermo-mechanical and inertial load. As a result, the case, tubesheet, flange, and mounting components have a reasonable safety margin to the allowable stress assuming a fatigue strength of Inconel 625 of 10000 cycles under 1000 K.

배관계통의 내진해석에 따른 응답조합과 누락질량효과

  • 이범수
    • Journal of the KSME
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    • 제25권4호
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    • pp.304-311
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    • 1985
  • 원자력발전소는 사고시 주변의 인구 및 환경에 미치는 영향의 심각성을 고려하여 가능한 모든 안전조치를 취하여 설계. 건설되도록 하고 있다. 특히 원자로냉각재 계통의 배관이 그러하며 고도의 안전성 및 신뢰성을 확보하기 위하여 지진에 대해서도 구조적인 건전성이 입증되어야 한다. 일반적으로 지진하중에 대한 배관계통의 내진해석에서는 층응답스펙트럼에 의한 모우드 해석 방법이 이용되고 있다. 이 때 내진해석으로 얻어진 응답의 조합에는 신중한 고려가 필요 하다. 즉 배관계통의 특성, 입력지진의 특성, 계산에 고려하는 모우드의 수등을 감안하여 적절한 응답조합이 이루어져야 한다. 본 해설에서는 여러 가지의 응답조합방법과 해석시 고려되는 모 우드의 수를 제한함으로써 발생하는 오차를 보정하기 위한 누락질량효과(missing mass effect)에 대하여 설명하고자 한다. 또 두 가지의 해석모델에 대하여 실제 내진 해석을 수행하여 그 결 과를 비교검토하기로 한다.

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Smart Structural Health Monitoring Using Carbon Nanotube Polymer Composites (탄소나노튜브 고분자 복합체 기반 스마트 구조건전성 진단)

  • Park, Young-Bin;Pham, Giang T.;Wang, Ben;Kim, Sang-Woo
    • Composites Research
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    • 제22권6호
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    • pp.1-6
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    • 2009
  • This paper presents an experimental study on the piezoresistive behavior of nanocomposite strain sensors subjected to various loading modes and their capability to detect structural deformations and damages. The electrically conductive nanocomposites were fabricated in the form of a film using various types of thermoplastic polymers and multi-walled carbon nanotubes (MWNTs) at various loadings. In this study, the nanocomposite strain sensors were bonded to a substrate and subjected to tension, flexure, or compression. In tension and flexure, the resistivity change showed dependence on measurement direction, indicating that the sensors can be used for multi-directional strain sensing. In addition, the sensors exhibited a decreasing behavior in resistivity as the compressive load was applied, suggesting that they can be used for pressure sensing. This study demonstrates that the nanocomposite strain sensors can provide a pathway to affordable, effective, and versatile structural health monitoring.