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초임계압 화력 과열기 구조의 고신뢰도 건전성 평가 방법
이형연,주용선,최현선,원민구,허남수 한국압력기기공학회 2020 한국압력기기공학회 논문집 Vol.16 No.1
Integrity evaluations on a platen superheater were conducted as per ASME Section VIII Division 2(hereafter ‘ASME VIII(2)’) which was originally used for design with implicit consideration of creep effects. A platen superheater subjected to severe loading conditions of high pressure and high temperature at creep regime in a supercritical thermal plant in Korea was chosen for present study. Additional evaluations were conducted as per nuclear-grade high-temperature design rule of RCC-MRx that takes creep effects into account explicitly. Comparisons of the two results from ASME VIII(2) and RCC-MRx were conducted to quantify the conservatism of ASME VIII(2). From present analyses, it was shown that the design evaluation results exceeded allowable limits of RCC-MRx for the plant design conditions although limits of ASME VIII(2) were satisfied regardless of operation time, which means that design as per ASME VIII(2) might be potentially non-conservative in case of operation in creep range. A high-temperature design evaluation program as per RCC-MRx, called ‘HITEP_RCC-MRx’ has been used and it was shown that pressure boundary components can be designed reliably with the program especially for the loading conditions of long-term creep conditions.
면진된 KALIMER 원자로 구조물의 내진설계 및 지진해석
이형연,구경희,유봉 한국지진공학회 1999 한국지진공학회논문집 Vol.3 No.1
본 연구에서는 현재 국내에서 면진설계를 적용하여 개발중인 KALIMER(Korea Advanced Llquid Metal Reactor) 액체금속로에 대한 내진설계 및 지진해석을 위하여 핵심구조물인 원자로구조물에 대한 단순 지진해석모델을 개발하였다 이를 이용하여 면진설계의 경우와 비면진 설계의 경우에 대한 동특성분석과 시간이력 지진해석을 수행하여 비교평가하였다. 또한 ASME 설계코드에 따른 응력한계요건을 검토하기 위하여 등가 지진응력해석을 수행하고 이로부터 내진여유도를 계산하였다 지진안전성에 대한 하나의 지표로서 원자로 구조물이 견딜수 있는 최대지진하중을 결정하기 위한 한계지진하중(Limit seismic load)을 저의하였다 지진해석결과 면진된 KALIMER 원자로구조믈은 비면진된 경우에 비하여 가속도응답과 구조물간의 상대변위응답이 현저히 감소하였고 충분한 내진여유도로 인하여 한계지진하중이 0.8g로 나타났다. In this paper, the seismic analysis model for seismically isolated KALIMER reactor structures is developed and the modal analysis and the seismic time history analysis are carried out for seismic isolation and non-isolation cases. To check the seismic stress limit according to the ASME Code, the equivalent seismic stress analyses are preformed using the 3-D finite element model. From the seismic stress analysis, the seismic margins are calculated for structural members. The limit of seismic load is defined to show that the maximum input acceleration ensures the structural safety for seismic load. In comparison of seismic responses between seismic isolation and non-isolation cases, the seismic isolation design gives significantly reduced acceleration responses and relative displacements between structures. The seismic margin of KALIMER reactor structure is high enough to produce the limit seismic load 0.8g.
이형연,이제환,최현선 한국압력기기공학회 2020 한국압력기기공학회 논문집 Vol.16 No.1
A number of so-called ‘Type IV’ cracking was reported to occur at the welded joints of the P91 steel or P92 steel reheat steam piping systems in Korean supercritical thermal power plants. The reheat steam piping systems are subjected to severe thermal and pressure loading conditions of coolant higher than 570C and 4MPa, respectively. In this study, piping analyses and design evaluations were conducted for the piping system of a specific thermal plant in Korea and suggestions were made how structural integrity could be improved so that type IV cracks at the welded joints could be prevented. Integrity evaluations were conducted as per ASME B31.1 code with implicit consideration of creep effects which was used in original design of the piping system and as per nuclear-grade RCC-MRx code with explicit consideration of creep effects. Comparisons were made between the evaluation results from the two design rules. Another approach with modification or reduction of the redundant supports in the piping systems was investigated as a tool to mitigate thermal stresses which should essentially contribute to prevention of Type IV cracking without major modification of the existing piping systems. In addition, a post weld heat treatment method and repair weld method which could improve integrity of the welded joint of P91 steel were investigated.
이형연,Jae-Hyuk Eoh,이용범 대한기계학회 2013 JOURNAL OF MECHANICAL SCIENCE AND TECHNOLOGY Vol.27 No.9
A high temperature design and creep-fatigue damage evaluation for a helical type sodium-to-air heat exchanger (AHX) in a 600MWe sodium-cooled fast reactor (SFR) has been conducted. The AHX is a safety-grade component in a passive decay heat removal (DHR)system. Safe and reliable decay heat removal is one of the most important tasks in the successful design of a sodium-cooled fast reactor. Therefore, independent, diverse and redundant DHR systems incorporating both passive and active mechanisms have been employed in the demonstration SFR developed by Korea Atomic Energy Research Institute (KAERI). One of the key DHR components is sodium-toair heat exchanger, which has a helically coiled tube arrangements. A creep-fatigue damage evaluation has been performed according to the elevated temperature design codes of ASME Subsection NH and RCC-MRx based on a full 3D finite element analysis. The integrity of the heat exchangers under creep-fatigue loading was confirmed and code comparisons were made as well.
Single-Layer 포텐셜과 가중함수를 이용한 응력강도계수의 계산
이형연,홍창선 대한기계학회 1995 대한기계학회논문집 Vol.19 No.4
A new weight function approach to determine SIF(stress intensity factor) using single-layer potential has been presented. The crack surface displacement field was represented by one boundary integral term whose kernel was modified from Kelvin's fundamental solution. The proposed method enables the calculation of SIF using only one SIF solution without any modification for the crack geometries symmetric in two-dimensional plane such as a center crack in a plate with or without an internal hole, double edge cracks, circumferential crack or radial cracks in a pipe. The application procedure to those crack problems is very simple and straightforward with only one SIF solution. The necessary information in the analysis is two reference SIFs. The analysis results using present closed-form solution were in good agreement with those of the literature.
이형연,이재한,유봉,Lee, Hyeong-Yeon,Lee, Jae-Han,Yoo, Bong 대한기계학회 1996 大韓機械學會論文集A Vol.20 No.7
An approximate weight function technique using the indirect boundary integral equation has been presented for the analysis of stress intensity foactors(SIFs) of a thick pipe. One-term boundary integral was introduced to represent the crack surface displacement field for the displacement based weight function technique. An explicit closed-form SIF solution applicable to symmetric cracked pipes without any modification of the solution including both circumferential and radial cracks has been derived. The necessary information in the analysis is two or three reference SIFs. In most cases the SIF solution were in good agreement with those available in the literature.