Development of a Web-Based Design Evaluation Platform for Elevated Temperature Design as per ASME Section III Division 5, ASME CC-2843 and RCC-MRx
Hyeong-Yeon Lee, Ki-Ean Nam, Nam‐Su Huh, Min-Kyu Kim
Korea Atomic Energy Research Institute Seoul National University of Science and Technology
阅读操作
确认中在文库中上传 PDF 后可生成中文音频讲解。
摘要与影响
An integrated web-based design evaluation platform of HITEP (HIgh Temperature design Evaluation Program) covering the three elevated temperature design rules of ASME BPVC Section III Division 5 Subsection HB (hereafter ‘ASME-HB’), ASME Code Case 2843-2 (hereafter ‘CC-2843’) and RCC-MRx, in addition to light water reactor design rules of ASME BPVC Section III Division 1 Subsection NB (hereafter ‘ASME-NB’) has been developed. CC-2843 is recently published code case of ASME Section VIII Division 2 based on the ASME-HB procedures with explicit consideration of creep. The evaluation module of ASME-NB has been added because the low-temperature design evaluations should be also conducted for a high-temperature component depending on temperature fluctuations. The HITEP platform can be used with high reliability and efficiency for the design of high temperature pressure boundary components or piping systems subjected to high-temperature operation at creep regime in a Generation IV nuclear reactor systems, renewable plants and advanced thermal power plants. In addition to those high-temperature applications, the platform can be applied to design of Generation III+ light water reactor systems. It was shown that the platform can be reliably and efficiently used for the elevated temperature design (hereafter ‘ETD’) of pressure boundary components and piping systems. The HITEP platform has been successfully used for the ETD of pressure boundary components and piping systems of the two large scale sodium test facilities of the STELLA-2 that is currently under operation and the thermal energy storage test facility of the TESET that is under construction at KAERI.
逐年被引趋势
关键指标
同类平均 = 1
同领域 · 同年份 · 同类型
Google Scholar 与 OpenAlex 的被引统计范围不同,数值存在差异属正常。
AI 辅助阅读
依据:摘要
可就本文提问;依据不足时会说明。
学术脉络
学科主题
工程Nuclear reactor physics and engineering
Nuclear Materials and Properties · Nuclear Engineering Thermal-Hydraulics
参考文献 0
引用本文 1
按被引量排序,此处列出前 3 条