• 文献检索
  • 文档翻译
  • 深度研究
  • 学术资讯
  • Suppr Zotero 插件Zotero 插件
  • 邀请有礼
  • 套餐&价格
  • 历史记录
应用&插件
Suppr Zotero 插件Zotero 插件浏览器插件Mac 客户端Windows 客户端微信小程序
定价
高级版会员购买积分包购买API积分包
服务
文献检索文档翻译深度研究API 文档MCP 服务
关于我们
关于 Suppr公司介绍联系我们用户协议隐私条款
关注我们

Suppr 超能文献

核心技术专利:CN118964589B侵权必究
粤ICP备2023148730 号-1Suppr @ 2026

文献检索

告别复杂PubMed语法,用中文像聊天一样搜索,搜遍4000万医学文献。AI智能推荐,让科研检索更轻松。

立即免费搜索

文件翻译

保留排版,准确专业,支持PDF/Word/PPT等文件格式,支持 12+语言互译。

免费翻译文档

深度研究

AI帮你快速写综述,25分钟生成高质量综述,智能提取关键信息,辅助科研写作。

立即免费体验

新提出的国际热核聚变实验堆偏滤器设计,采用在钨上插入碳的方式来减轻边界局域模以及对附近部件的二次辐射效应。

New proposed ITER divertor design using carbon insert on tungsten to mitigate ELMs and secondary radiation effects on nearby components.

作者信息

Sizyuk V, Hassanein A

机构信息

Center for Materials Under Extreme Environment (CMUXE), Purdue University, West Lafayette, IN, 47907, USA.

出版信息

Sci Rep. 2022 Mar 18;12(1):4698. doi: 10.1038/s41598-022-08837-2.

DOI:10.1038/s41598-022-08837-2
PMID:35304581
原文链接:https://pmc.ncbi.nlm.nih.gov/articles/PMC8933477/
Abstract

Building a successful device for the magnetic fusion energy production is a great challenge. ITER is an international project of the tokamak based magnetic fusion design being developed for the demonstration of the feasibility of thermonuclear technologies for future realization of successful commercial fusion energy. A key obstacle to a successful magnetic fusion energy production is however, the performance during abnormal events including plasma disruptions and edge-localized modes (ELMs). A credible reactor design must tolerate at least a few of these transient events without serious consequences such as melting of the structure. This paper investigates and compares the performance of the current ITER tokamak design during two types of transient events, i.e., ELMs occurring at normal operation and disruptions during abnormal operation. We simulated the divertor components response using our integrated 3D HEIGHTS package. The simulations include self-consistent modeling of the interaction of the released core plasma particles with the initial solid divertor material, energy deposition processes, vaporization of divertor material, secondary plasma formation and MHD evolution, incident core particles collisions and scattering from this dense secondary plasma, photon radiation of secondary plasma, and the resulting heat loads on nearby components. Our simulations showed that using a small carbon insert around the strike point can significantly reduce the overall expected damage on the tungsten dome structure, reflector plates, and prevent tungsten vaporization and its potential core plasma contamination.

摘要

建造一个用于磁聚变能源生产的成功装置是一项巨大的挑战。国际热核聚变实验堆(ITER)是一个基于托卡马克的磁聚变设计的国际项目,旨在展示热核技术的可行性,以便未来成功实现商业聚变能源。然而,成功进行磁聚变能源生产的一个关键障碍是包括等离子体破裂和边缘局域模(ELM)在内的异常事件期间的性能。一个可靠的反应堆设计必须能够承受至少一些此类瞬态事件,而不会产生诸如结构熔化等严重后果。本文研究并比较了当前ITER托卡马克设计在两种瞬态事件中的性能,即在正常运行期间发生的ELM和异常运行期间的破裂。我们使用集成的3D HEIGHTS软件包模拟了偏滤器部件的响应。模拟包括对释放的核心等离子体粒子与初始固体偏滤器材料的相互作用、能量沉积过程、偏滤器材料的汽化、二次等离子体形成和磁流体动力学演化、入射核心粒子与这种密集二次等离子体的碰撞和散射、二次等离子体的光子辐射以及对附近部件产生的热负荷进行自洽建模。我们的模拟表明,在打击点周围使用小的碳插入物可以显著降低对钨穹顶结构、反射板的总体预期损伤,并防止钨汽化及其对核心等离子体的潜在污染。

https://cdn.ncbi.nlm.nih.gov/pmc/blobs/a6fd/8933477/f57f0963ec1f/41598_2022_8837_Fig9_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/a6fd/8933477/1f8302f105b6/41598_2022_8837_Fig1_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/a6fd/8933477/342bfccab295/41598_2022_8837_Fig2_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/a6fd/8933477/eefa370267c8/41598_2022_8837_Fig3_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/a6fd/8933477/82bc8f13a9de/41598_2022_8837_Fig4_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/a6fd/8933477/08b1a12bbb2d/41598_2022_8837_Fig5_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/a6fd/8933477/af60c7101212/41598_2022_8837_Fig6_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/a6fd/8933477/c399a2f9360c/41598_2022_8837_Fig7_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/a6fd/8933477/7591ac75a782/41598_2022_8837_Fig8_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/a6fd/8933477/f57f0963ec1f/41598_2022_8837_Fig9_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/a6fd/8933477/1f8302f105b6/41598_2022_8837_Fig1_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/a6fd/8933477/342bfccab295/41598_2022_8837_Fig2_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/a6fd/8933477/eefa370267c8/41598_2022_8837_Fig3_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/a6fd/8933477/82bc8f13a9de/41598_2022_8837_Fig4_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/a6fd/8933477/08b1a12bbb2d/41598_2022_8837_Fig5_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/a6fd/8933477/af60c7101212/41598_2022_8837_Fig6_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/a6fd/8933477/c399a2f9360c/41598_2022_8837_Fig7_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/a6fd/8933477/7591ac75a782/41598_2022_8837_Fig8_HTML.jpg
https://cdn.ncbi.nlm.nih.gov/pmc/blobs/a6fd/8933477/f57f0963ec1f/41598_2022_8837_Fig9_HTML.jpg

相似文献

1
New proposed ITER divertor design using carbon insert on tungsten to mitigate ELMs and secondary radiation effects on nearby components.新提出的国际热核聚变实验堆偏滤器设计,采用在钨上插入碳的方式来减轻边界局域模以及对附近部件的二次辐射效应。
Sci Rep. 2022 Mar 18;12(1):4698. doi: 10.1038/s41598-022-08837-2.
2
Potential design problems for ITER fusion device.国际热核聚变实验堆(ITER)聚变装置的潜在设计问题。
Sci Rep. 2021 Jan 22;11(1):2069. doi: 10.1038/s41598-021-81510-2.
3
Liquid lithium as divertor material to mitigate severe damage of nearby components during plasma transients.液态锂作为偏滤器材料,以减轻等离子体瞬态期间附近部件的严重损坏。
Sci Rep. 2022 Nov 5;12(1):18782. doi: 10.1038/s41598-022-21866-1.
4
Upgrade of Langmuir probe diagnostic in ITER-like tungsten mono-block divertor on experimental advanced superconducting tokamak.在实验先进超导托卡马克装置的仿国际热核聚变实验堆钨单块偏滤器中对朗缪尔探针诊断系统的升级。
Rev Sci Instrum. 2016 Aug;87(8):083504. doi: 10.1063/1.4960181.
5
Runaway electrons and their interaction with tungsten wall: a comprehensive study of effects.逃逸电子及其与钨壁的相互作用:效应的综合研究
Sci Rep. 2023 Dec 8;13(1):21760. doi: 10.1038/s41598-023-48672-7.
6
Novel concept suppressing plasma heat pulses in a tokamak by fast divertor sweeping.通过快速偏滤器扫描抑制托卡马克中等离子体热脉冲的新概念。
Sci Rep. 2022 Oct 11;12(1):17013. doi: 10.1038/s41598-022-18748-x.
7
Design of the DEMO Fusion Reactor Following ITER.ITER之后的DEMO聚变反应堆设计。
J Res Natl Inst Stand Technol. 2009 Aug 1;114(4):229-36. doi: 10.6028/jres.114.016. Print 2009 Jul-Aug.
8
Real-time feedback control of the impurity emission front in tokamak divertor plasmas.托卡马克偏滤器等离子体中杂质发射前沿的实时反馈控制。
Nat Commun. 2021 Feb 17;12(1):1105. doi: 10.1038/s41467-021-21268-3.
9
Reduction of edge-localized mode intensity using high-repetition-rate pellet injection in tokamak H-mode plasmas.在托卡马克H模等离子体中使用高重复率弹丸注入降低边缘局域模强度
Phys Rev Lett. 2013 Jun 14;110(24):245001. doi: 10.1103/PhysRevLett.110.245001. Epub 2013 Jun 11.
10
Anomaly classification by inserting prior knowledge into a max-tree based method for divertor hot spot characterization on WEST tokamak.通过将先验知识插入基于最大树的方法对WEST托卡马克偏滤器热点特征进行异常分类。
Rev Sci Instrum. 2023 Aug 1;94(8). doi: 10.1063/5.0156956.

引用本文的文献

1
Managing the heat: In-Vessel Components.热管理:堆内构件
Philos Trans A Math Phys Eng Sci. 2024 Oct 9;382(2280):20230408. doi: 10.1098/rsta.2023.0408. Epub 2024 Aug 26.
2
Isotope engineering achieved by local coordination design in Ti-Pd co-doped ZrCo-based alloys.通过局部配位设计在Ti-Pd共掺杂ZrCo基合金中实现同位素工程。
Nat Commun. 2024 Apr 3;15(1):2883. doi: 10.1038/s41467-024-47250-3.
3
Runaway electrons and their interaction with tungsten wall: a comprehensive study of effects.逃逸电子及其与钨壁的相互作用:效应的综合研究

本文引用的文献

1
Potential design problems for ITER fusion device.国际热核聚变实验堆(ITER)聚变装置的潜在设计问题。
Sci Rep. 2021 Jan 22;11(1):2069. doi: 10.1038/s41598-021-81510-2.
Sci Rep. 2023 Dec 8;13(1):21760. doi: 10.1038/s41598-023-48672-7.
4
Liquid lithium as divertor material to mitigate severe damage of nearby components during plasma transients.液态锂作为偏滤器材料,以减轻等离子体瞬态期间附近部件的严重损坏。
Sci Rep. 2022 Nov 5;12(1):18782. doi: 10.1038/s41598-022-21866-1.