http://chineseinput.net/에서 pinyin(병음)방식으로 중국어를 변환할 수 있습니다.
변환된 중국어를 복사하여 사용하시면 됩니다.
사고압력 조건에서 기하학적 특성을 고려한 원자로 격납건물 거동해석
백용락,신재철 忠南大學校 産業技術硏究所 1996 산업기술연구논문집 Vol.11 No.1
In this study, effects of the representative geometrical feature of a reactor containment structure on the structural responses for accident pressure are analyzed. The analysis is carried out for the containment structure of YongGwang unit 3 & 4, which is a standardized nuclear power plant in Korea. The representative geometry of the structure such as buttress, opening and reinforced section surrounding the opening is considered as a variable in the analysis. The analysis results show that the geometrical effects on the responses are significant. From the results, the essential consideration items in the analysis of the structure for accident pressure are derived for comparison of the analysis and the test results, and items to be improved are proposed to establish a plan for measuring the exact responses in case of structural integrity test (SIT) of the structure. The adequacy of the two-dimensional axisymmetric model for the analysis, which is a commonly used model, is investigated and the region unaffected by the geometrical feature is also estimated for constructing a partial model of the structure for the detailed design of the section near a equipment hatch.
백용락,정인수,신재철,이상국 忠南大學校 産業技術硏究所 1996 산업기술연구논문집 Vol.11 No.2
In most countries road bridges are subjected to increasingly heavy freight traffic with a number of exceptional truck loads. This has made it necessary to devote particular attention to the evaluation of safety and load-carrying capacity of bridges, which is a vital process in the decision-making for maintenance, repair, strengthening, or even replacement of existing road bridges. However, most countries including Korea do not have a comprehensive rating system or rating code. Furthermore, the current methods of rating of road bridges are dependent on the conventional design concepts and the safety parameters of the current bridge design codes. A practical reliability model for the safety assessment and rating of existing PC beam bridges are developed by explicitly incorporating the degree of deterioration and damages based on available inspection or field test data. AFOSM methods are used for the reliability analysis of the proposed models. The proposed reliability model and methods are applied to the safety assessment of existing PC beam bridges in Korea.