期刊
NUCLEAR ENGINEERING AND TECHNOLOGY
卷 54, 期 1, 页码 401-413出版社
KOREAN NUCLEAR SOC
DOI: 10.1016/j.net.2021.08.001
关键词
Reactor vessel nozzle; Nozzle corner; Stress intensity factor; Stress concentration factor; Finite element analysis
资金
- Nuclear Safety Research Program through the Korea Foundation of Nuclear Safety (KoFONS) - Nuclear Safety and Security Commission (NSSC) of the Republic of Korea [1805005]
This paper presents a simple method for estimating the cross-section stress profiles of nozzles designed according to ASME Code Section III. The effectiveness of the method is validated through comparison with finite element analysis results.
This paper provides a simple method by which to estimate the cross-section stress profiles for nozzles designed according to ASME Code Section III. Further, this method validates the effectiveness of earlier work performed by the authors on standard nozzles. The method requires only the geometric information of the pressure vessel and the attached nozzle. A PWR direct vessel injection nozzle, a PWR outlet nozzle, a PWR inlet nozzle and a BWR recirculation outlet nozzle are selected based on their corresponding specific designs, e.g., a varying nozzle radius, a varying nozzle thickness and an outlet nozzle boss. A cross-section stress profile comparison shows that the estimates are in good agreement with the finite element analysis results. Differences in stress intensity factors calculated in accordance with ASME BPVC Section XI Appendix G are discussed. In addition, a change in the dimensions of an alternate nozzle design relative to the standard values is discussed, focusing on the stress concentration factors of the nozzle inside corner. (c) 2021 Korean Nuclear Society, Published by Elsevier Korea LLC. This is an open access article under the CC BY-NC-ND license (http://creativecommons.org/licenses/by-nc-nd/4.0/).
作者
我是这篇论文的作者
点击您的名字以认领此论文并将其添加到您的个人资料中。
推荐
暂无数据