• 대한기계학회논문집A
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• 제41권10호
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• pp.941-948
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• 2017

최근 화석연료 고갈 및 환경오염 문제를 해결할 수 있는 대안으로 수소에너지가 주목받고 있으며, 고효율 및 주행거리 향상을 위한 수소 자동차 개발에 따라 수소 저장 압력용기의 내용적 증가 및 구조안전성이 요구되고 있다. 그러나, 반구형의 바닥부보다 내용적이 큰 타원형 바닥부의 형상설계가 이루어지지 않았으며, 타원형 바닥부의 성형공정에 관한 연구 또한 미비한 실정이다. 이에 본 연구에서는 수소압력용기 라이너의 타원형 바닥부 장단축비에 따른 최대 내용적을 계산하고 유한요소해석을 통한 구조안전성 검증 및 이에 대한 이론적 고찰을 검토하였다. 또한, 바닥부 성형 공정해석을 통하여 제안된 최대 내용적을 갖는 타원형상의 성형 가능성을 확보하였다.

• 한국해양공학회지
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• 제19권2호
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• pp.40-46
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• 2005

In order to consider the statistical properties of probability variables which are used in structural analysis, the conventional approach of using safety factors based on past experience, are usually used to estimate the safety of a structure. The real structures could only be analyzed with the error in estimation of loads, materials and dimensional characteristics. Errors should be considered systematically in the structural analysis. In this paper, we estimated the probability of failure of two pressure vessels, simultaneously, using computational analysis. One pressure vessel, theoretically, had no stiffener whereas the other had. This paper also discusses sensitivity values of random variables in the rounded parts of the pressure vessel which had ring-style stiffener in the center of the external area which had ring-style stiffener. Finally, we show that the reliability index, and the probability of failure, can be calculated to particular tolerance limits.

• Nuclear Engineering and Technology
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• 제36권6호
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• pp.512-527
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• 2004

This paper describes the finite element (FE) analysis results of a 1/4 scale model of a prestressed concrete containment vessel (PCCV) by considering the tension stiffening effect, which is a result of the bond effect between the concrete and the steel. The tension stiffening model is assumed to be an exponential form based on the relationship between the average stress and the average strain of the concrete. The objective of the present FE analysis is to evaluate the ultimate internal pressure capacity of the PCCV, as well as its failure mechanism, when the PCCV model is subjected to a monotonous internal pressure beyond is design pressure capacity. With the commercial code ABAQUS, the FE analysis used two concrete failure criteria: a 2-dimensional axi-symmetric model with modified Drucker-Prager failure criteria and a 3-dimensional model with a damaged plasticity mod디. The results of our FE analysis on the ultimate pressure capacity and failure modes of PCCV have a good agreement with the experimental data.

• 대한기계학회논문집
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• 제17권10호
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• pp.2634-2645
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• 1993

Dome structures of pressure vessels subjected to internal pressure are usually analyzed by linear elastic theory assuming small deformation. Geometric and material nonlinear behaviors appear in actual dome structures because of large deformation and loads exceeding yield strength. In this paper, linear and nonlinear analyses were performed for various hemispherical and torispherical domes to check the effects of geometric and material nonliearity on the stress and displacement by the finite element method. The effect of the geometric nonlinearity decreased the stress levels a lot for very thin general torispherical domes, which enables more realistic and effective design. The material nonlinear effects are negligible for hemispherical and optimum torispherical domes, and those are large for most of the general torispherical domes.

• 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.

• Nuclear Engineering and Technology
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• 제31권4호
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• pp.408-422
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• 1999

To reduce the fast neutron fluence which deteriorates the RPV integrity, additional shields were assumed to be installed at the outer core structures of the Kori Unit 1 reactor, and its reduction effects were examined. Full scope Monte Carlo simulation with MCNP4A code was made to estimate the fast neutron fluence at the RPV. An optimized design option was found from various choices in geometry and material for shield structure. It was expected that magnitude of fast neutron fluence would be reduced by 39% at the circumferential weld of the RPV, resulting in extension of plant lifetime by 4.6 EFPYs based on the criterion of PTS requirement It was investigated that the nuclear characteristics and thermal hydraulic factors at the internal core were only negligibly influenced by the installation of additional shield structure.

• 한국산학기술학회논문지
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• 제21권2호
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• pp.66-73
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• 2020

현재 개발되고 있는 수소 압축 사이클에서는 압축기를 통해 초고압으로 압축된 수소를 고압용기 내에 저장하여 사용한다. 이러한 충전과정 중 용기내의 수소의 압력 및 온도 상승으로 인하여 고압용기에서 열응력이 발생할 수 있다. 고압용기의 신뢰성을 확보하기 위해서는 용기내의 수소의 온도를 예측하고 제어하는 것이 중요하다. 본 논문에서는 이러한 고압용기의 신뢰성 해석을 위하여 50 MPa급 수소압축시스템에서 고압용기를 충전하는 과정에서의 압력상승에 따른 용기 내의 수소온도 변화 및 외부와의 열평형까지 걸리는 시간, 감압밸브를 지날 때의 수소온도 변화, 고압용기 냉각을 위한 열교환기의 요구능력 등에 대하여 이론적인 방법과 수치적인 방법으로 해석을 수행하였다. 이론해석 결과, 고압용기의 내부 온도는 충전하기 전에 40 ℃에서 충전 후 1^st cycle, 2^nd cycle에서 평균적으로 126.675 ℃, 62.1 ℃가 증가하였다. 또한, 고압용기의 충전량은 1^st cycle, 2^nd cycle에서 각각 7.9 kg, 8.9 kg으로 계산되었다. 본 연구의 결과는 수소충전소와 같이 수소압축시스템이 필요한 현장의 인프라 설계 및 구축 등에 유용하게 활용 될 것이다.

• 한국가스학회:학술대회논문집
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• 한국가스학회 2003년도 추계학술발표회 논문집
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• pp.77-84
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• 2003

• 한국신재생에너지학회:학술대회논문집
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• 한국신재생에너지학회 2007년도 추계학술대회 논문집
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• pp.193-196
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• 2007

We developed and tested the high pressure hydrogen gas cylinder(type4) for fuel cell vehicle. The working pressure is 350bar. We conducted material tests, production tests and design qualification tests on the developed cylinders according to modified NGV2-2000(hydrogen). The high pressure hydrogen gas cylinder met all the design qualification requirements of ANSI/CSA NGV2-2000 and acquired NGV2 certification from independent inspection agency.

• 한국해양공학회:학술대회논문집
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• 한국해양공학회 2003년도 춘계학술대회 논문집
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• pp.43-47
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• 2003

This paper presents the optimum design of cylindrical shell under external pressure loading. Two kinds of material, AI7075-T6, Ti-6AI-4V, are considered. For each material, the design variable is a thickness of the unstiffened parallel middle body shell, and the state variable, constraint, is hoop stress and the object function is total weight of the cylindrical shell. Optimization is performed by conventional FE Program, ANSYS. In addition, buckling analysis is performed for the middle body of the cylindrical shell. Finally, we calculates the payload of the cylindrical shell to keep neutral buoyancy with optimized thickness in deep-sea applications.