• 대한기계학회논문집A
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• 제34권11호
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• pp.1773-1778
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• 2010

본 논문은 원자력 내진등급 원전용 주냉각수 펌프의 지진하중에 대한 구조 건전성을 코드에 따라 평가하였다. 펌프 구조물을 3차원 모델링하여 유한요소법을 사용하여 모달 해석 및 응답스펙트럼 해석을 수행하였다. 모달 해석 결과 고유진동수, 모드형상 및 모드참여계수를 얻을 수 있었다. 응력해석에서 구한 응력들을 조합하여 원자력 규격집에서 제시한 허용응력과 비교하여 펌프의 구조 건전성을 판단하였다. 모든 지진하중에 대한 펌프 구조물에서의 응력은 허용값 보다 작게 분포하므로 구조적 건전성을 유지한다고 평가할 수 있다.

• Nuclear Engineering and Technology
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• 제56권2호
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• pp.359-374
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• 2024

A high-fidelity numerical analysis methodology was proposed for evaluating the fuel rod cladding integrity of a Prototype Gen IV Sodium Fast Reactor (PGSFR) during normal operation and Design basis events (DBEs). The MARS-LMR code, system transient safety analysis code, was applied to analyze the DBEs. The results of the MARS-LMR code were used as boundary condition for a 3D computational fluid dynamics (CFD) analysis. The peak temperatures considering HCFs satisfied the cladding temperature limit. The temperature and pressure distributions were calculated by ANSYS CFX code, and applied to structural analysis. Structural analysis was performed using ANSYS Mechanical code. The seismic reactivity insertion SSE accident among DBEs had the highest peak cladding temperature and the maximum stress, as the value of 87 MPa. The fuel cladding had over 40 % safety margin, and the strain was below the strain limit. Deformation behavior was elucidated for providing relative coordinate data on each active fuel rod center. Bending deformation resulted in a flower shape, and bowing bundle did not interact with the duct of fuel assemblies. Fuel rod maximum expansion was generated with highest stress. Therefore, it was concluded that the fuel rod cladding of the PGSFR has sufficient structural safety margin during DBEs.

• 한국산학기술학회논문지
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• 제20권8호
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• pp.23-28
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• 2019

본 연구에서는 선박 및 해양플랜트에 사용되어지는 유체기기에 관하여 공동에 의한 손상을 줄이기 위해 표면 금속코팅을 적용할 경우 구조건전성을 평가하고 효율개선을 위한 수치해석적 결과에 대해 기술하였다. 소재 경량화 및 표면 코팅을 통해 날개 두께 등이 얇아지더라도 구조 강도와 성능이 확보됨을 간접적으로 입증하기 위해 코팅 하지 않은 경우, 코팅 후 동일 두께, 코팅 후 두께 3% 경량화 그리고, 코팅 후 두께 5% 경량화 것의 4 가지 모델에 대해 코팅의 유효성을 해석적 방법으로 평가하였다. 코팅 전 후 및 두께를 3% 줄여 무게를 경량화한 경우에 대해 구조해석을 수행한 결과, 응력은 7% 증가하였고 안전율은 2.7%로 나타났으며 기준 안전율인 1보다 큰 값이 도출되었다. 코팅 전 후및 두께를 5% 줄여 무게를 경량화한 경우에 대해 구조해석을 수행한 결과, 응력은 12%까지 증가하였고 안전율은 0.99%로 나타났으며 0.1% 정도 차이로 안전율이 확보되지 않음에 따라 구조건전성이 부족한 것으로 나타났다. 하지만 부족한 안전율은 좀 더 좋은 소재를 선정하거나 코팅두께를 현재보다 두껍게 한다면 충분한 안전율을 확보할 수 있다고 판단된다. 최종적으로 코팅을 함으로 인해 구조건전성이 개선되는 것을 확인하였고, 5% 경량화한 경우에도 코팅의 효과로 인해 충분히 구조건전성이 확보될 수 있음을 확인하였다.

• 대한기계학회:학술대회논문집
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• 대한기계학회 2003년도 춘계학술대회
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• pp.279-284
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• 2003

A nuclear power plant is composed of a number of primary components. Maintaining the integrity of these components is one of the most critical issues in nuclear industry. In order to maintain the integrity of these primary components, a complicated procedure is required including regular in-service inspection, failure assessment, fracture mechanics analysis, etc. Also, experts in different fields have to co-operate to resolve the integrity issues on the basis of inspection results. This integrity evaluation process usually takes long, and thus, is detrimental for the plant productivity. Therefore, an effective safety evaluation system is essential to manage the integrity issues on a nuclear power plant. In this paper, a web-based fatigue life evaluation system for primary components in nuclear power plant is proposed. This system provides engineering knowledge-based information and concurrent and collaborative working environment through internet, and thus, is expected to raise the efficiency of integrity evaluation procedures on primary components of a nuclear power plant.

• 대한기계학회논문집A
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• 제36권9호
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• pp.1047-1052
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• 2012

가압경수로형 원전의 Alloy 600 원자로압력용기헤드 관통노즐 및 Alloy 82/182 이종금속 맞대기 용접부에서 일차수응력부식균열(PWSCC)이 보고된 이후 전 세계적으로 PWSCC에 의한 용접부 파단을 예방하기 위해 강화검사를 적용하고 있다. 본 이종금속용접부에 대한 가동중검사에서 균열이 발견된 경우 건전성평가 결과가 도출되기까지 발전소가 정지 상태에 있게 됨에 따라 원전 이용율 저하가 발생할 수 있는데, 이를 예방하기 위해서는 균열건전성평가 관련 기술의 정립뿐만 아니라 신속하게 평가 결과를 도출할 수 있는 시스템의 구축이 필요하다. 본 연구에서는 이종금속 맞대기 용접부를 대상으로 진행하고 있는 PWSCC 균열건전성평가 기준 정립 및 전산 시스템 개발 결과를 제시하였다. 본 연구를 통해 이종금속 맞대기 용접부 PWSCC 균열건전성평가 기술이 정립되고 전산 시스템으로 구현되어 원자로압력용기 주변 이종금속 맞대기 용접부에서의 PWSCC 균열에 대한 기술적 건전성평가 수단을 확보하였다.

• Nuclear Engineering and Technology
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• 제28권4호
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• pp.373-378
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• 1996

The CANFLEX fuel bundle has been developed by KAERI/AECL jointly to facilitate the use of various fuel cycles in CANDU-6 reactor. The structural analysis of the fuel bundles by hydraulic drag force is performed to evaluate the fuel integrity during the refuelling service. The present analysis method is newly developed for the structural integrity valuation by studying FEM modelling for the fuel bundles in a fuel channel. As compared the results of the mechanical strength test the displacement value of endplate given by analysis results shoo6 to be good agreement within 15% under the maximum design drag load. As the results of analysis, it is shown to keep the structural integrity of CANFLEX fuel bundles under hydraulic drag load during the refuelling service.

• 대한기계학회:학술대회논문집
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• 대한기계학회 2001년도 추계학술대회논문집A
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• pp.161-165
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• 2001

Bogie frame of the electric car is an important structural member for the support of vehicle loading. In general, more than 25 years' durability is necessary. Much study has been carried out for the prediction of the structural integrity of the bogie frame in experimental and theoretical domains. One of the useful methods is reliability-based approach. The objective of this paper is to estimate the structural integrity of the bogie frame of an electric car, which is under the running test. We used two approachs. In the first approach probabilistic distribution of S-N curve is used. In the second approach, limit state function is used.

• Nuclear Engineering and Technology
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• 제41권3호
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• pp.347-354
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• 2009

Welding is required for a connection between two different components in the nuclear fuel of a pressurized water reactor. This work relies on a mechanical experiment and analytic results to investigate the structural integrity of nuclear fuel in a situation where some components are not welded to each other. A series of lateral vibration tests are performed in a test facility, and the test structures are examined in terms of dynamic behavior. In the tests, the displacement signal at every grid structure that sustains fuel rods is measured and processed to identify the dynamic properties. The fluid-elastic stability of the structure is also analyzed to evaluate susceptibility to a cross flow with an assumed conservative cross flow distribution. The test and analysis results confirm that the structural integrity can be maintained even in the absence of some welding connections.

• 한국정밀공학회지
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• 제6권4호
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• pp.94-102
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• 1989

The effect of plastic strain on the surface integrity of mild steel (SS 41) was studied. This paper shows that the recrystallization technique is adequate to evaluate the plastic strain in a machined surface experimentally. The relations between the plastic strain and the machining conditions are quantitatively evaluated by using the recrystallization technique. The obtained results are summarized as follows. 1. The surface integrity of steel is considerably influenced by the amount of surface region deformation produced by changes in cutting conditions. 2. The plastic strain in machined surface produced by changes of the cutting conditions is evaluated by the recyrstallization technique. 3. The plastic strain increases with the increase of depth of cut and the decrease of rake angle. 4. When the cutting force is high and the rake angle is small, the value of maximum true strain reaches to high. 5. The maximum true strain is related to the cutting energy, and the values increase with the increase of the unit shear and total engergy in constant depth with the increase of the energy values.

• 대한안전경영과학회:학술대회논문집
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• 대한안전경영과학회 2008년도 춘계학술대회
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• pp.185-196
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• 2008

The objective of this study is to evaluate the mechanical behaviors and structural integrity of the weldment of high strength steel by using an acoustic emission (AE) techniques. Simple tension and AE tests were conducted against the 3 kind of welding test specimens. In order to analysis the effectiveness of weldability, joinability and structural integrity, we used K-means clustering method as a unsupervised learning pattern recognition algorithm for obtained multivariate AE main data sets, such as AE counts, energy, amplitude, hits, risetime, duration, counts to peak and rms signals. Through the experimental results, the effectiveness of the proposed method is discussed.