Zobrazeno 1 - 10
of 18
pro vyhledávání: '"Shin-Beom Choi"'
Publikováno v:
Nuclear Engineering and Technology, Vol 51, Iss 6, Pp 1681-1688 (2019)
In accordance with ASME Boiler and Pressure Vessel (B&PV) Code Sec.XI Appendix. G, a postulated crack is located at the beltline of a reactor pressure vessel because the neutron flux at the beltline is higher than elsewhere. This means that the dista
Autor:
In-Ju Hwang, Joo-Dong Kim, Jae-Boong Choi, Song-Chun Choi, Jung Min Lee, Shin-Beom Choi, Moon Ki Kim
Publikováno v:
Journal of Mechanical Science and Technology. 28:3759-3767
The present paper aims to suggest a web-based LNG (Liquefied natural gas) plant management system that is applicable from the design stage through the operational lifetime of the plant. The usefulness of this program is maximized by combining a virtu
Publikováno v:
Journal of manufacturing engineering & technology. 22:573-579
Once-through helically coiled steam generator tubes subjected to external pressure are of interest because of their application to advanced small- and medium-sized integral reactors, in which a primary coolant with a relatively higher pressure flows
Autor:
Hyun-Min Jang, Dong-Yun Lee, Jae-Boong Choi, Ki-Chul Myung, Tae-Young Ryu, Sang-Mo Yang, Shin-Beom Choi
Publikováno v:
Transactions of the Korean Society of Mechanical Engineers A. 36:1535-1542
Key Words:FiniteElementMethod(유한요소법),Large-ScaleAnalysis(대규모해석),ThermalFatigue(열피로),HeatRecoverySteamGenerator(배열회수증기발생기)초록:배열회수증기발생기는복합발전플랜트에서사용되는주요기
Publikováno v:
Volume 3: Design and Analysis.
The aim of this paper is to evaluate the constraint effect due to the crack location and bottom head shape. To do so, two types of bottom head shape such as a semi-spherical bottom head and semi-elliptical bottom head were considered. In addition, fi
Publikováno v:
Volume 6A: Materials and Fabrication.
The final goal of this study is to solve the round-robin problem for the safety of a reactor pressure vessel by adopting a finite element analysis and probabilistic fracture mechanics. To do so, a sensitivity analysis and a deterministic analysis sho
Publikováno v:
Nuclear Engineering and Technology. 44:791-798
Since standardized fracture test specimens cannot be easily extracted from in-service components, several alternative fracture toughness test methods have been proposed to characterize the deformation and fracture resistance of materials. One of the
Publikováno v:
Journal of Mechanical Science and Technology. 26:2727-2734
Although the well-known master curve method has been widely used to estimate the ductile to brittle transition temperature and to prevent subsequent brittle fracture of reactor pressure vessels, it has a limitation to determine reference temperatures
Autor:
Han-Ok Ko, Jae-Uk Jeong, Jae-Boong Choi, Bong-Sang Lee, Min-Chul Kim, Yoon-Suk Chang, Shin-Beom Choi
Publikováno v:
Transactions of the Korean Society of Mechanical Engineers A. 36:513-521
The aim of this study was to determine the brittle fracture behavior of reactor pressure vessel steel by considering the temperature dependence of a damage model. A multi-island genetic algorithm was linked to a Weibull stress model, which is the mod
Autor:
Shin-Beom Choi, Young Jin Kim, Young Hwan Choi, Yoon-Suk Chang, Jae-Boong Choi, Myung-Jo Jhung
Publikováno v:
Nuclear Engineering and Technology. 42:590-599
Recently, efficient operation and practical management of power plants have become important issues in the nuclear industry. In particular, typical aging parameters such as stress and cumulative usage factor should be determined accurately for contin