An investigation of structural integrity of CSB − for normal contact with RV outlet nozzle

IF 1.9 3区工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Nuclear Engineering and Design Pub Date : 2024-11-15 DOI:10.1016/j.nucengdes.2024.113704

Niniek Ramayani Yasintha, Omondi Christopher Ondwasi, Namgung Ihn

{"title":"An investigation of structural integrity of CSB − for normal contact with RV outlet nozzle","authors":"Niniek Ramayani Yasintha, Omondi Christopher Ondwasi, Namgung Ihn","doi":"10.1016/j.nucengdes.2024.113704","DOIUrl":null,"url":null,"abstract":"<div><div>This research is about improving the design of Core Support Barrel (CSB) by eliminating the gap between its hot-leg opening and the reactor vessel (RV) outlet nozzle. This gap causes significant bypass flow, impacting reactor performance. A proposed design modification aimed to establish contact between these components, requiring a thorough analysis of the contact interface. The study determined that a contact overlap of 15 mm meets ASME code standards and other relevant criteria. Moreover, this design improvement offers the added benefit of enhancing the seismic response of the reactor internals due to the increased horizontal support provided by the RV outlet nozzle to the CSB. Modal analysis revealed a substantial upward shift in the CSB’s natural frequency from 15.6 Hz-20.7 Hz to 21.9 Hz-38 Hz, representing a more than 40 % increase. The research demonstrates that the proposed design effectively eliminates bypass flow, and significantly improves the seismic response of the reactor internals.</div></div>","PeriodicalId":19170,"journal":{"name":"Nuclear Engineering and Design","volume":"430 ","pages":"Article 113704"},"PeriodicalIF":1.9000,"publicationDate":"2024-11-15","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear Engineering and Design","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0029549324008045","RegionNum":3,"RegionCategory":"工程技术","ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"Q1","JCRName":"NUCLEAR SCIENCE & TECHNOLOGY","Score":null,"Total":0}

引用次数: 0

Abstract

This research is about improving the design of Core Support Barrel (CSB) by eliminating the gap between its hot-leg opening and the reactor vessel (RV) outlet nozzle. This gap causes significant bypass flow, impacting reactor performance. A proposed design modification aimed to establish contact between these components, requiring a thorough analysis of the contact interface. The study determined that a contact overlap of 15 mm meets ASME code standards and other relevant criteria. Moreover, this design improvement offers the added benefit of enhancing the seismic response of the reactor internals due to the increased horizontal support provided by the RV outlet nozzle to the CSB. Modal analysis revealed a substantial upward shift in the CSB’s natural frequency from 15.6 Hz-20.7 Hz to 21.9 Hz-38 Hz, representing a more than 40 % increase. The research demonstrates that the proposed design effectively eliminates bypass flow, and significantly improves the seismic response of the reactor internals.

查看原文

微信好友朋友圈 QQ好友复制链接

本刊更多论文

CSB 与 RV 出口喷嘴正常接触的结构完整性调查

这项研究旨在改进堆芯支撑筒（CSB）的设计，消除其热脚开口与反应堆容器（RV）出口喷嘴之间的间隙。该间隙会导致大量旁路流，影响反应堆性能。拟议的设计修改旨在建立这些组件之间的接触，需要对接触界面进行全面分析。研究确定，15 毫米的接触重叠符合 ASME 规范标准和其他相关标准。此外，由于 RV 出口喷嘴增加了对 CSB 的水平支撑，这一设计改进还能增强反应堆内部的地震响应。模态分析显示，CSB 的固有频率从 15.6 Hz-20.7 Hz 大幅上移至 21.9 Hz-38Hz，增幅超过 40%。研究表明，拟议的设计有效地消除了旁路流，并显著改善了反应堆内部的地震响应。

本文章由计算机程序翻译，如有差异，请以英文原文为准。

求助全文

约1分钟内获得全文去求助

来源期刊

Nuclear Engineering and Design 工程技术-核科学技术

CiteScore

3.40

自引率

11.80%

发文量

377

审稿时长

5 months

期刊介绍： Nuclear Engineering and Design covers the wide range of disciplines involved in the engineering, design, safety and construction of nuclear fission reactors. The Editors welcome papers both on applied and innovative aspects and developments in nuclear science and technology. Fundamentals of Reactor Design include: • Thermal-Hydraulics and Core Physics • Safety Analysis, Risk Assessment (PSA) • Structural and Mechanical Engineering • Materials Science • Fuel Behavior and Design • Structural Plant Design • Engineering of Reactor Components • Experiments Aspects beyond fundamentals of Reactor Design covered: • Accident Mitigation Measures • Reactor Control Systems • Licensing Issues • Safeguard Engineering • Economy of Plants • Reprocessing / Waste Disposal • Applications of Nuclear Energy • Maintenance • Decommissioning Papers on new reactor ideas and developments (Generation IV reactors) such as inherently safe modular HTRs, High Performance LWRs/HWRs and LMFBs/GFR will be considered; Actinide Burners, Accelerator Driven Systems, Energy Amplifiers and other special designs of power and research reactors and their applications are also encouraged.