Final optics for laser-driven inertial fusion reactors

J. Woodworth, L. Chase, M. Guinan, W. Krupke, W.R. Sooy
{"title":"Final optics for laser-driven inertial fusion reactors","authors":"J. Woodworth, L. Chase, M. Guinan, W. Krupke, W.R. Sooy","doi":"10.1109/FUSION.1991.218705","DOIUrl":null,"url":null,"abstract":"A promising concept for the final optics of a baseline laser-driven ICF (inertial confinement fusion) reactor is described. It addresses the problem of long-term survival of the final optics with respect to neutron damage. The use of refractive optics is considered. A baseline design consists of two wedges of fused silica, which put a dogleg into the beam and thus remove optics further upstream from direct sight of the reactor. If the closest optic were located 40 m from the center of a 3-GWt reactor, it would be subject to an average 14-MeV neutron flux of approximately=5*10/sup 12/ n/s-cm/sup 2/ with a peak flux of approximately=6*10/sup 18/ n/s-cm/sup 2/. A major question to be answered is: What duration of reactor operation can this optic withstand? To answer this question, the literature bearing on radiation-induced optical damage in fused silica was reviewed to assess its implications for reactor operation with the baseline final optics scheme. It appears possible to continuously anneal the neutron damage in the silica by keeping the wedge at a modestly elevated temperature. The literature review indicates that the proposed final optic material-fused silica-is structurally resistant to radiation damage and that if operated at a temperature of about 300 degrees C will remain optically clear.<<ETX>>","PeriodicalId":318951,"journal":{"name":"[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering","volume":"225 1","pages":"0"},"PeriodicalIF":0.0000,"publicationDate":"1991-10-02","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"2","resultStr":null,"platform":"Semanticscholar","paperid":null,"PeriodicalName":"[Proceedings] The 14th IEEE/NPSS Symposium Fusion Engineering","FirstCategoryId":"1085","ListUrlMain":"https://doi.org/10.1109/FUSION.1991.218705","RegionNum":0,"RegionCategory":null,"ArticlePicture":[],"TitleCN":null,"AbstractTextCN":null,"PMCID":null,"EPubDate":"","PubModel":"","JCR":"","JCRName":"","Score":null,"Total":0}
引用次数: 2

Abstract

A promising concept for the final optics of a baseline laser-driven ICF (inertial confinement fusion) reactor is described. It addresses the problem of long-term survival of the final optics with respect to neutron damage. The use of refractive optics is considered. A baseline design consists of two wedges of fused silica, which put a dogleg into the beam and thus remove optics further upstream from direct sight of the reactor. If the closest optic were located 40 m from the center of a 3-GWt reactor, it would be subject to an average 14-MeV neutron flux of approximately=5*10/sup 12/ n/s-cm/sup 2/ with a peak flux of approximately=6*10/sup 18/ n/s-cm/sup 2/. A major question to be answered is: What duration of reactor operation can this optic withstand? To answer this question, the literature bearing on radiation-induced optical damage in fused silica was reviewed to assess its implications for reactor operation with the baseline final optics scheme. It appears possible to continuously anneal the neutron damage in the silica by keeping the wedge at a modestly elevated temperature. The literature review indicates that the proposed final optic material-fused silica-is structurally resistant to radiation damage and that if operated at a temperature of about 300 degrees C will remain optically clear.<>
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
激光驱动惯性聚变反应堆的最终光学
描述了基线激光驱动ICF(惯性约束聚变)反应堆的最终光学的一个有前途的概念。它解决了最终光学器件在中子损伤方面的长期生存问题。考虑了折射光学的使用。基线设计由两个熔融硅楔组成,将光束放入狗腿状,从而使光学元件远离反应器的直接视线。如果最近的光学元件位于距离3-GWt反应堆中心40 m处,则其平均14-MeV中子通量约=5*10/sup 12/ n/s-cm/sup 2/,峰值通量约=6*10/sup 18/ n/s-cm/sup 2/。需要回答的一个主要问题是:这种光学器件能承受多长时间的反应堆运行?为了回答这个问题,我们回顾了有关熔融二氧化硅中辐射引起的光学损伤的文献,以评估其对基线最终光学方案的反应堆操作的影响。似乎有可能通过将楔体保持在适度升高的温度来连续退火二氧化硅中的中子损伤。文献综述表明,所提出的最终光学材料熔融二氧化硅在结构上抗辐射损伤,并且如果在约300摄氏度的温度下操作,将保持光学清晰度
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
Design of a coil to correct magnetic field errors on the DIII-D tokamak The charge exchange recombination diagnostic system on the DIII-D tokamak Software upgrade for the DIII-D neutral beam control systems Timing system for neutral beam injection on the DIII-D tokamak DIII-D radiation shielding procedures and experiences
×
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