• 대한조선학회논문집
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• 제30권2호
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• pp.161-176
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• 1993

본 논문에서는 주어진 상황에 맞추어 적절한 수준에서 건전성평가를 수행하기 위하여, 개정된 BSI PD 6493의 3단계 평가방법에 균열성장효과를 고려한 건전성 평가방법과 균열의 안정성장을 엄밀히 고려할 수 있는 안정성 평가방법(stability assessment method:SAM)과 더불어 소성 붕괴를 평가하는 극한하중해석을 고려한 건전성 평가방법을 정식화하였다. 또한 신뢰성이론 중 2차 모멘트방법을 사용하여, center cracked panel(CCP) 시편과 관통균열을 갖는 파이프에 대하여, 신뢰성해석에 의한 건전성 평가를 수행하였다. 신뢰성해석을 수행하는데 필요한 확률변수들의 통계적 특성은 지금까지 보고된 그들 변수들의 실험자료와 통계해석의 결과들을 이용하였다. 또 기존의 신뢰성해석에서 정확한 파괴확률을 구할 수 있는 Monte Carlo 방법을 사용하여, 본 논문의 유용성을 검토하였다.

• 한국정밀공학회:학술대회논문집
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• 한국정밀공학회 2012년도 추계학술대회 논문집
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• pp.763-764
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• 2012

• 한국전산구조공학회:학술대회논문집
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• 한국전산구조공학회 1995년도 봄 학술발표회 논문집
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• pp.73-81
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• 1995

In Korea, the pilot construction of the first high-speed railroad on the Seoul-Pusan has already started 2 years ago. In the thesis, an attempt is made to develop reliability-based integrity-assessment models for the computer-aided control and maintenance of high-speed railroad bridges. The strength limit state models for PC railroad bridges encompass the bending and shear strengths as well as the strength interaction equations which simultaneously take into the element and system reliablities of the proposed limit states and reliability models. Then, the actual load carrying capacity and the realistic safety of bridges are evaluated using the system reliability-based equivalent strength, and the results are compared with those of the element reliability-based or conventional methods. Various parametric studies are performed for the proposed reliability-based safety and integrity-assessment models using the actual PC box girder bridges used in the pilot construction. And the sensitivity analyses are performed for the basic random variables included in strength limit state models. It is concluded that proposed models may be practically applied for the rational assessment of safety and integrity of high speed railroad bridges.

• 한국항공우주학회지
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• 제37권1호
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• pp.105-112
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• 2009

전투기가 임무수행중 기체에 발생할 수 있는 전투손상에 대처하기 위해 손상평가 및 수리설계, 구조건전성 평가방법 등 손상 후속절차를 연구하였다. 사례로서 F-15 ECS Bay에 발생한 전투손상에 대하여 ABDR(Aircraft Battle Damage Repair) 기술을 적용하여 손상평가 및 수리설계를 수행하고, 그 내용과 절차를 양식에 정리하였다. 또한, 정적강도 및 피로수명 계산과 같이 수리설계 구조의 구조건전성을 평가하여 비행안전 여부를 입증하고 영구수리 시점을 판단하였다.

• International Journal of Safety
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• 제10권2호
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• pp.1-5
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• 2011

The structural integrity assessment of APR1400 (Advanced Power Reactor 1400) reactor vessel internals has been being performed referring the US Nuclear Regulatory Commission regulatory guide 1.20 comprehensive vibration assessment program prior to commercial operation. The program is composed of a hydraulic and structural analysis, a vibration measurement, and an inspection. This paper describes the hydraulic and structural analysis on the reactor vessel internals due to hydraulic loads caused by the turbulence of reactor coolant. Three-dimensional models were built for the hydraulic and structural analysis and then hydraulic loads and structural responses were predicted for five analysis cases with CFX and ANSYS respectively. The structural responses show that the APR1400 reactor vessel internals have sufficient structural integrity in comparison with the acceptance criteria.

• 한국가스학회:학술대회논문집
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• 한국가스학회 2003년도 추계학술발표회 논문집
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• pp.37-42
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• 2003

• 한국압력기기공학회 논문집
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• 제13권1호
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• pp.16-39
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• 2017

This paper reviewed and summarized the experimental studies conducted during last three decades to evaluate the structural integrity and to establish the acceptance criteria for piping system of nuclear power plants (NPPs) under seismic loading condition. These experimental studies contain the results of large-scale piping system tests under excessive seismic loading as well as standard specimen tests, simplified piping specimen tests, and piping components tests under simplified dynamic and cyclic loading. These would be useful as a basis for establishing integrity assessment procedure and acceptance criteria for piping systems of NPPs under beyond design basis earthquake (BDBE) conditions, and also could be used in planing the scope and direction of further related researches.

• 전산구조공학
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• 제20권3호
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• pp.14-17
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• 2007

• 한국소음진동공학회논문집
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• 제21권12호
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• pp.1098-1103
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• 2011

The structural integrity of APR1400 reactor vessel internals has been being assessed referring the US Nuclear Regulatory Commission regulatory guide 1.20, comprehensive vibration assessment program. The program is composed of a vibration and stress analysis, a vibration and stress measurement, and an inspection. This paper covers the vibration and stress analysis on the reactor vessel internals by the pulsation of reactor coolant pump. 3-dimensional models to calculate the hydraulic loads and structural responses were built and the pressure distributions and the structural responses were predicted using ANSYS. This paper presents that APR1400 reactor vessel internals have enough structural integrity against the pulsation of reactor coolant pump as the peak stress of the reactor vessel internals is much lower than the acceptance limit.

• 한국소음진동공학회:학술대회논문집
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• 한국소음진동공학회 2012년도 춘계학술대회 논문집
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• pp.907-910
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• 2012

Since the inner barrel assembly of the Advanced Power Reactor 1400 reactor vessel is a new design feature introduced instead of CEA(control element assembly) shroud assembly, the inner barrel assembly can be a significant object of structural integrity assessment. This paper covers the structural responses of top plate, which is a component of the inner barrel assembly, against the deterministic hydraulic load induced by pump pulsation and the random hydraulic load induced by turbulence of coolant. The top plate responds to the deterministic hydraulic load more than to the random hydraulic load and shows enough structural integrity. The results of this paper will be important basis for the selection of instruments and measurement location.