在系统层面上评价DEMO WCLL育种毯部门的热工性能

IF 2 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Francesco Colliva , Fabio Giannetti , Antonio Trotta , Alessandro Del Nevo , Gianfranco Caruso , Cristiano Ciurluini
{"title":"在系统层面上评价DEMO WCLL育种毯部门的热工性能","authors":"Francesco Colliva ,&nbsp;Fabio Giannetti ,&nbsp;Antonio Trotta ,&nbsp;Alessandro Del Nevo ,&nbsp;Gianfranco Caruso ,&nbsp;Cristiano Ciurluini","doi":"10.1016/j.fusengdes.2025.115483","DOIUrl":null,"url":null,"abstract":"<div><div>In the last years, an intense research activity has been carried out within the framework of the EUROfusion Consortium to optimize the layout of the EU-DEMO Breeding Blanket (BB). Two main concepts are currently under investigation: the Helium-Cooled Pebble Bed and the Water-Cooled Lead-Lithium, that is the option object of this work. This layout relies on pressurized water as coolant, liquid metal (i.e., lead-lithium) as breeder, neutron multiplier and tritium carrier, and reduced-activation ferritic/martensitic steel as structural material. In addition, a thin tungsten armor is used to protect the First Wall component. The overall BB is constituted by sixteen toroidal sectors. Each sector is composed by inboard (two) and outboard (three) segments, considering their radial position with respect to the plasma chamber. At its time, the segments consist in a stack of vertically-piled breeding cells, that are the system elementary units. Their layout differs according to the poloidal position and the segment they belong.</div><div>To obtain an affordable BB design, one of the key issues is assessing its thermal-hydraulic performances during operational and accidental conditions. For this, an analysis of the component transient behavior is needed to improve and refine the project. To achieve this goal, during the last year, the Nuclear Engineering Research Group of Sapienza University of Rome, in collaboration with ENEA, has developed a detailed model of the DEMO WCLL BB sector, including both the inboard and outboard segments. The rationale has been dividing the overall stack of cells belonging to each segment in poloidal sections. The number of these sections has been the object of a sensitivity study. The preliminary objective of this work is to have a dedicated BB sector model to evaluate its thermal-hydraulic performances at a system level during the DEMO normal operations, considering the pulsed plasma regime and the spatial distributions of the various loads insisting on this component. In addition, the developed input deck allowed to have insights into the BB behavior during accidental conditions, demonstrating the capability of the current design to effectively withstand such scenarios without exceeding safety margins. The level of detail adopted to prepare the BB model enabled to preliminary exclude the occurrence of local damaging phenomena, such as thermal crisis.</div></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":"222 ","pages":"Article 115483"},"PeriodicalIF":2.0000,"publicationDate":"2025-10-11","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"On the evaluation of the DEMO WCLL Breeding Blanket sector thermal-hydraulic performances at a system level\",\"authors\":\"Francesco Colliva ,&nbsp;Fabio Giannetti ,&nbsp;Antonio Trotta ,&nbsp;Alessandro Del Nevo ,&nbsp;Gianfranco Caruso ,&nbsp;Cristiano Ciurluini\",\"doi\":\"10.1016/j.fusengdes.2025.115483\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><div>In the last years, an intense research activity has been carried out within the framework of the EUROfusion Consortium to optimize the layout of the EU-DEMO Breeding Blanket (BB). Two main concepts are currently under investigation: the Helium-Cooled Pebble Bed and the Water-Cooled Lead-Lithium, that is the option object of this work. This layout relies on pressurized water as coolant, liquid metal (i.e., lead-lithium) as breeder, neutron multiplier and tritium carrier, and reduced-activation ferritic/martensitic steel as structural material. In addition, a thin tungsten armor is used to protect the First Wall component. The overall BB is constituted by sixteen toroidal sectors. Each sector is composed by inboard (two) and outboard (three) segments, considering their radial position with respect to the plasma chamber. At its time, the segments consist in a stack of vertically-piled breeding cells, that are the system elementary units. Their layout differs according to the poloidal position and the segment they belong.</div><div>To obtain an affordable BB design, one of the key issues is assessing its thermal-hydraulic performances during operational and accidental conditions. For this, an analysis of the component transient behavior is needed to improve and refine the project. To achieve this goal, during the last year, the Nuclear Engineering Research Group of Sapienza University of Rome, in collaboration with ENEA, has developed a detailed model of the DEMO WCLL BB sector, including both the inboard and outboard segments. The rationale has been dividing the overall stack of cells belonging to each segment in poloidal sections. The number of these sections has been the object of a sensitivity study. The preliminary objective of this work is to have a dedicated BB sector model to evaluate its thermal-hydraulic performances at a system level during the DEMO normal operations, considering the pulsed plasma regime and the spatial distributions of the various loads insisting on this component. In addition, the developed input deck allowed to have insights into the BB behavior during accidental conditions, demonstrating the capability of the current design to effectively withstand such scenarios without exceeding safety margins. The level of detail adopted to prepare the BB model enabled to preliminary exclude the occurrence of local damaging phenomena, such as thermal crisis.</div></div>\",\"PeriodicalId\":55133,\"journal\":{\"name\":\"Fusion Engineering and Design\",\"volume\":\"222 \",\"pages\":\"Article 115483\"},\"PeriodicalIF\":2.0000,\"publicationDate\":\"2025-10-11\",\"publicationTypes\":\"Journal Article\",\"fieldsOfStudy\":null,\"isOpenAccess\":false,\"openAccessPdf\":\"\",\"citationCount\":\"0\",\"resultStr\":null,\"platform\":\"Semanticscholar\",\"paperid\":null,\"PeriodicalName\":\"Fusion Engineering and Design\",\"FirstCategoryId\":\"5\",\"ListUrlMain\":\"https://www.sciencedirect.com/science/article/pii/S0920379625006799\",\"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}","platform":"Semanticscholar","paperid":null,"PeriodicalName":"Fusion Engineering and Design","FirstCategoryId":"5","ListUrlMain":"https://www.sciencedirect.com/science/article/pii/S0920379625006799","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

摘要

在过去的几年中,在欧洲融合联盟的框架内开展了一项激烈的研究活动,以优化EU-DEMO育种毯(BB)的布局。目前正在研究的两个主要概念是:氦冷却卵石床和水冷铅锂,这是这项工作的选择对象。这种布局依赖于压水水作为冷却剂,液态金属(即铅锂)作为增殖剂、中子倍增器和氚载体,低活化铁素体/马氏体钢作为结构材料。此外,一个薄的钨装甲被用来保护第一墙组件。整个BB由16个环形扇区组成。考虑到它们相对于等离子腔室的径向位置,每个扇区由内侧(两个)和外侧(三个)部分组成。在它的时间,区段包括在一堆垂直堆积繁殖细胞,这是系统的基本单位。它们的布局根据极向位置和它们所属的段而不同。为了获得经济实惠的BB设计,关键问题之一是评估其在操作和事故条件下的热工性能。为此,需要对组件瞬态行为进行分析,以改进和细化项目。为了实现这一目标,去年,罗马Sapienza大学核工程研究小组与ENEA合作,开发了DEMO WCLL BB部门的详细模型,包括舷内和舷外部分。其基本原理是在极向切片中划分属于每个部分的整个细胞堆栈。这些部分的数量一直是敏感性研究的对象。这项工作的初步目标是建立一个专用的BB扇区模型,在DEMO正常运行期间,考虑脉冲等离子体状态和坚持该组件的各种负载的空间分布,在系统层面评估其热工性能。此外,开发的输入平台可以深入了解BB在意外情况下的行为,证明当前设计能够在不超过安全边际的情况下有效承受这种情况。在制作BB模型时所采用的细节水平可以初步排除局部破坏现象的发生,如热危机。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
On the evaluation of the DEMO WCLL Breeding Blanket sector thermal-hydraulic performances at a system level
In the last years, an intense research activity has been carried out within the framework of the EUROfusion Consortium to optimize the layout of the EU-DEMO Breeding Blanket (BB). Two main concepts are currently under investigation: the Helium-Cooled Pebble Bed and the Water-Cooled Lead-Lithium, that is the option object of this work. This layout relies on pressurized water as coolant, liquid metal (i.e., lead-lithium) as breeder, neutron multiplier and tritium carrier, and reduced-activation ferritic/martensitic steel as structural material. In addition, a thin tungsten armor is used to protect the First Wall component. The overall BB is constituted by sixteen toroidal sectors. Each sector is composed by inboard (two) and outboard (three) segments, considering their radial position with respect to the plasma chamber. At its time, the segments consist in a stack of vertically-piled breeding cells, that are the system elementary units. Their layout differs according to the poloidal position and the segment they belong.
To obtain an affordable BB design, one of the key issues is assessing its thermal-hydraulic performances during operational and accidental conditions. For this, an analysis of the component transient behavior is needed to improve and refine the project. To achieve this goal, during the last year, the Nuclear Engineering Research Group of Sapienza University of Rome, in collaboration with ENEA, has developed a detailed model of the DEMO WCLL BB sector, including both the inboard and outboard segments. The rationale has been dividing the overall stack of cells belonging to each segment in poloidal sections. The number of these sections has been the object of a sensitivity study. The preliminary objective of this work is to have a dedicated BB sector model to evaluate its thermal-hydraulic performances at a system level during the DEMO normal operations, considering the pulsed plasma regime and the spatial distributions of the various loads insisting on this component. In addition, the developed input deck allowed to have insights into the BB behavior during accidental conditions, demonstrating the capability of the current design to effectively withstand such scenarios without exceeding safety margins. The level of detail adopted to prepare the BB model enabled to preliminary exclude the occurrence of local damaging phenomena, such as thermal crisis.
求助全文
通过发布文献求助,成功后即可免费获取论文全文。 去求助
来源期刊
Fusion Engineering and Design
Fusion Engineering and Design 工程技术-核科学技术
CiteScore
3.50
自引率
23.50%
发文量
275
审稿时长
3.8 months
期刊介绍: The journal accepts papers about experiments (both plasma and technology), theory, models, methods, and designs in areas relating to technology, engineering, and applied science aspects of magnetic and inertial fusion energy. Specific areas of interest include: MFE and IFE design studies for experiments and reactors; fusion nuclear technologies and materials, including blankets and shields; analysis of reactor plasmas; plasma heating, fuelling, and vacuum systems; drivers, targets, and special technologies for IFE, controls and diagnostics; fuel cycle analysis and tritium reprocessing and handling; operations and remote maintenance of reactors; safety, decommissioning, and waste management; economic and environmental analysis of components and systems.
×
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
确定
请完成安全验证×
copy
已复制链接
快去分享给好友吧!
我知道了
右上角分享
点击右上角分享
0
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 布克学术 All rights reserved.
京ICP备2023020795号-1
ghs 京公网安备 11010802042870号
Book学术文献互助
Book学术文献互助群
群 号:604180095
Book学术官方微信