Methods for forecasting performance limits of fusion reactor structural materials

G.E. Lucas, G.R. Odette
{"title":"Methods for forecasting performance limits of fusion reactor structural materials","authors":"G.E. Lucas,&nbsp;G.R. Odette","doi":"10.1016/0167-899X(85)90009-6","DOIUrl":null,"url":null,"abstract":"<div><p>For the purposes of both developing appropriate alloys for fusion reactors and ultimately designing and building such devices, it is necessary to determine the mechanical response to high energy neutron irradiation of candidate structural materials. The current and near-term facilities for providing the requisite testing environment are either limited by dissimilarity to fusion reactor environments (i.e., fission reactors), or irradiation volume, or both. This necessitates the development of both a testing technology commensurate with the available facilities — i.e., primarily small specimen technology — and a correlation methodology which recognizes the limitations of the anticipated data base and maximizes the use of that data. In this paper we (1) describe a general philosophy for such correlation methodologies, (2) provide a brief overview of small specimen test techniques and data characteristics, and (3) demonstrate with several examples how correlations can be developed and applied.</p></div>","PeriodicalId":82205,"journal":{"name":"Nuclear engineering and design/fusion : an international journal devoted to the thermal, mechanical, materials, structural, and design problems of fusion energy","volume":"2 1","pages":"Pages 145-173"},"PeriodicalIF":0.0000,"publicationDate":"1985-01-01","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"https://sci-hub-pdf.com/10.1016/0167-899X(85)90009-6","citationCount":"11","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"Nuclear engineering and design/fusion : an international journal devoted to the thermal, mechanical, materials, structural, and design problems of fusion energy","FirstCategoryId":"1085","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/0167899X85900096","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"","JCRName":"","Score":null,"Total":0}
引用次数: 11

Abstract

For the purposes of both developing appropriate alloys for fusion reactors and ultimately designing and building such devices, it is necessary to determine the mechanical response to high energy neutron irradiation of candidate structural materials. The current and near-term facilities for providing the requisite testing environment are either limited by dissimilarity to fusion reactor environments (i.e., fission reactors), or irradiation volume, or both. This necessitates the development of both a testing technology commensurate with the available facilities — i.e., primarily small specimen technology — and a correlation methodology which recognizes the limitations of the anticipated data base and maximizes the use of that data. In this paper we (1) describe a general philosophy for such correlation methodologies, (2) provide a brief overview of small specimen test techniques and data characteristics, and (3) demonstrate with several examples how correlations can be developed and applied.

查看原文
分享 分享
微信好友 朋友圈 QQ好友 复制链接
本刊更多论文
核聚变反应堆结构材料性能极限预测方法
为了开发适合聚变反应堆的合金,并最终设计和建造这样的装置,有必要确定候选结构材料在高能中子辐照下的力学响应。目前和近期提供必要测试环境的设施,要么与聚变反应堆环境(即裂变反应堆)不同,要么受到辐照量的限制,或者两者兼而有之。这就需要发展一种与现有设施相称的测试技术- -即主要是小样本技术- -和一种认识到预期数据库的局限性并最大限度地利用该数据的相关方法。在本文中,我们(1)描述了这种相关方法的一般原理,(2)提供了小样本测试技术和数据特征的简要概述,(3)用几个例子展示了如何开发和应用相关性。
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
自引率
0.00%
发文量
0
期刊最新文献
Preface Announcement Cryopumping for fusion reactors 2.1. Development of low activation Al alloys for the R-project 6. Research and development on the tritium handling technology in the R-project
×
引用
GB/T 7714-2015
复制
MLA
复制
APA
复制
导出至
BibTeX EndNote RefMan NoteFirst NoteExpress
×
×
提示
您的信息不完整,为了账户安全,请先补充。
现在去补充
×
提示
您因"违规操作"
具体请查看互助需知
我知道了
×
提示
现在去查看 取消
×
提示
确定
0
微信
客服QQ
Book学术公众号 扫码关注我们
反馈
×
意见反馈
请填写您的意见或建议
请填写您的手机或邮箱
已复制链接
已复制链接
快去分享给好友吧!
我知道了
×
扫码分享
扫码分享
Book学术官方微信
Book学术文献互助
Book学术文献互助群
群 号:481959085
Book学术
文献互助 智能选刊 最新文献 互助须知 联系我们:info@booksci.cn
Book学术提供免费学术资源搜索服务,方便国内外学者检索中英文文献。致力于提供最便捷和优质的服务体验。
Copyright © 2023 Book学术 All rights reserved.
ghs 京公网安备 11010802042870号 京ICP备2023020795号-1