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유한요소법을 이용한 원자로 압력용기의 압력-온도 한계곡선 평가
이규만(Gyu-Mahn lee),김종욱(Jong-Wook Kim),박근배(Keun-Bae Park) 대한기계학회 2001 대한기계학회 춘추학술대회 Vol.2001 No.8
To prevent the potential failure of the reactor pressure vessel (RPV), it is requested to operate RPV according to the pressure-temperature (P-T) limit curve during the heat-up and cool-down process. The procedure to make the P-T limit curve was suggested in the ASME Code but has been known to be too conservative for some cases. In this paper, the conservatism of the ASME Code Sec. XI, App. G was investigated by performing a series of finite element analyses. Also The effects of four different parameters including cladding thickness, fracture toughness, cooling rate, and neutron fluence were observed based on advanced analyses.
SMART 원자로 노내계측기 지지 구조물의 접수 진동 특성
이규만(Gyu Mahn Lee),안광현(Kwanghyun Ahn),이강헌(Kang Heon Lee),이재선(Jae Seon Lee) 대한기계학회 2020 大韓機械學會論文集A Vol.44 No.9
원자로 내진 해석 시 해석 효율을 위해 복잡한 원자로 형상을 1차원 보 요소로 등가하여 해석하는 방법이 주로 활용된다. 1차원 등가 해석 모델 생성 시 원자로 냉각재에 의한 유체 부가 질량 효과를 고려하기 위해서는 일반적으로 각 기기별 등가 모델에 부가 질량을 추가하거나 등가 유체 보 요소 등을 활용한다. 정상 운전 시 항상 접수 상태에 있는 다른 구조물과는 달리 SMART 원자로의 노내계측기 지지 구조물의 경우 구조물에 접하는 냉각재 자유 수면의 수위가 운전 조건에 따라 상시적으로 변화하므로 유체의 부가 질량 효과에 따른 구조물의 동특성이 정상 상태에서도 변화하는 특성을 가지고 있다. 본 연구에서는 주변 냉각재 수위 변화에 따른 SMART 원자로의 노내계측기 지지 구조물에 대한 동특성 변화를 분석하고 정량화하여 향후 내진 모델 작성 시 효율적으로 활용될 수 있도록 한다. One-dimensional equivalent model is widely utilized to improve the efficiency of a time-history seismic analysis for a nuclear reactor with complicated shape and arrangement. In the equivalent model, the added mass effect caused by the reactor coolant can be considered using a fluid element or adding a fluid mass to the structural model. In contrast to other structures whose whole part is submerged in the reactor coolant, a part of the in-core instrument support structure in a SMART is submerged in the reactor coolant, and the submerged volume changes as per reactor operating condition. Thus, in this study, the acoustic modal characteristics of an in-core instrument support structure was quantitatively investigated under various coolant levels. The results of this study can be utilized for the development of seismic model for in-core instrument support structure.
내재된 균열을 가진 원자로압력용기의 가압열충격하의 파괴역학적 건전성 해석
김종욱(Jong-Wook Kim),이규만(Gyu-Mahn Lee),김태완(Tae-Wan Kim),박근배(Keun-Bae Park) 대한기계학회 2008 대한기계학회 춘추학술대회 Vol.2008 No.5
The RPV integrity is ensured by a proper margin between its loads bearing capacity given by vessel design and the acting loads, which could occur during a plant operation. The objective of this study is to evaluate the integrity of the embedded crack in a RPV under a pressurized thermal shock condition by applying deterministic fracture mechanics. The three-dimensional finite element analyses, including the thermal and mechanical calculations, were performed using the finite element analysis program.
최우석(Woo-Seok Choi),이규만(Gyu-Mahn Lee),김태완(Tae-Wan Kim),김종인(Jong-In Kim) 대한기계학회 2007 대한기계학회 춘추학술대회 Vol.2007 No.5
The reactor head structure assembly(RHSA) is the structure located on the reactor assembly. The purpose of the assembly is providing interface location for cables, preventing pipe whips, prohibiting instruments from becoming missiles, and restraining CEDMs' horizontal motion. On the RHSA, reactor disconnect panels(RDP) are installed. The installation location of RDP is to be decided to minimize the geometric interface with other components. Since the neighborhood of RHSA is crowded due to many connectors and cables, it is necessary to find the good design of RHSA to make an intricate situation attenuated and the required function maintained. The geometric shape and overall configuration of RHSA are determined by axiomatic design approach. The FRs of RHSA are specified and the corresponding DPs are found to satisfy FRs in sequence. The finite element analysis is carried out based on the result of the axiomatic design to evaluate the structural integrity.
정경훈(Jeong, Kyeong-Hoon),이규만(Lee, Gyu-Mahn),김태완(Kim, Tae-Wan),박근배(Park, Keun-Bae) 한국소음진동공학회 2008 한국소음진동공학회 논문집 Vol.18 No.1
An analytical method for the free vibration of a flexible rectangular plate in contact with water is developed by the Rayleigh-Ritz method. The plate clamped along the edges is partially contacted with water at both sides. It is assumed that the contained water is incompressible and inviscid. The wet mode shape of the plate is assumed as a combination of the dry mode shapes of a clamped beam. The liquid motion is described by using the liquid displacement potential and determined by using the compatibility conditions along the liquid interface with the plate. Minimizing the Rayleigh quotient based on the energy conservation gives an eigenvalue problem. It is found that the theoretical results can predict excellently the fluid-coupled natural frequencies comparing with the finite element analysis result.