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원자로용기 결함 조건에 따른 원자로 내부구조물 이상진동에 대한 유한요소 해석
고태영(Taeyoung Ko),정도연(Doyun Jung),최영철(Youngchul Choi) 한국소음진동공학회 2023 한국소음진동공학회 논문집 Vol.33 No.6
In this study, a finite element analysis model for a real-scale reactor was developed to simulate abnormal vibration signal data of the reactor vessel internals (RVIs). The abnormal signals were simulated by setting the degree of fault of 54 stud bolts to a value between 0 and 1. The accuracy of the analytical model was verified by confirming that the predicted beam mode of approximately 8 and the shell mode of approximately 15 matched the actual reactor signals when the RVIs were in a normal state. A total of 54 simulations according to the fault degree of the stud bolts were performed based on the finite element analysis model.
APR1400 원자로 내부배럴집합체 상부판 구조응답해석
김규형(Kyu Hyung Kim),고도영(Do Young Ko),김성환(Sung Hwan Kim) 한국소음진동공학회 2012 한국소음진동공학회 학술대회논문집 Vol.2012 No.4
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.
원자로내부구조물 종합진동평가 수행을 위한 구조해석 방법론 개발 및 검증
구자영(Ja Yeong Gu),김규형(Kyu Hyung Kim),김용수(Yong Soo Kim) 대한기계학회 2010 대한기계학회 춘추학술대회 Vol.2010 No.11
The US NRC, in regulatory guide 1.20 (RG 1.20), requires the performance of a comprehensive vibration assessment program (CVAP) for reactor vessel internals (RVIs) to verify their structural integrity during the plant life time. The CVAP is generally composed of analysis, measurement, inspection and evaluation programs. In this study we focus on a structural analysis in the analysis program. The structural analysis methodology based on the RG 1.20(rev.3) was developed by using the 3 dimensional finite element method (FEM). The methodology is applied to analysis to predict the structural responses caused by pump pulsation and turbulent flow. To verify the methodology, the analysis results from this study were compared with the measured data of the RVI CVAP for Yonggwang Unit 4. The analysis results presented properly characteristics of structural responses induced by hydraulic loads and agreed well with the measured data in an acceptable error range. The methodology developed in this study can be used for structural analysis of other reactor internals.
A Study on Segmentation Process of the K1 Reactor Vessel and Internals
황영환,황석주,홍성훈,박광수,김남균,정덕원,김천우 한국방사성폐기물학회 2019 방사성폐기물학회지 Vol.17 No.4
After the permanent shutdown of K1 in 2017, decommissioning processes have attracted great attention. According to the current decommissioning roadmap, the dismantling of the activated components of K1 may start in 2026, following the removal of its spent fuel. Since the reactor vessel (RV) and reactor vessel internal (RVI) of K1 contain massive components and are relatively highly activated, their decommissioning process should be conducted carefully in terms of radiological and industrial safety. For achieving maximum efficiency of nuclear waste management processes for K1, we present activation analysis of the segmentation process and waste classification of the RV and RVI components of K1. For RVI, the active fuel regions and some parts of the upper and lower active regions are classified as intermediate-level waste (ILW), while other components are classified as low-level waste (LLW). Due to the RVI’s complex structure and high activation, we suggest various underwater segmentation techniques which are expected to reduce radiation exposure and generate approximately nine ILW and nineteen very low level waste (VLLW)/LLW packages. For RV, the active fuel region and other components are classified as LLW, VLLW, and clearance waste (CW). In this case, we suggest in-situ remote segmentation in air, which is expected to generate approximately forty-two VLLW/LLW packages.