欧盟 DEMO 育种材料活化和放射性核素清单分析评估

IF 1.9 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY Fusion Engineering and Design Pub Date : 2024-07-24 DOI:10.1016/j.fusengdes.2024.114605
{"title":"欧盟 DEMO 育种材料活化和放射性核素清单分析评估","authors":"","doi":"10.1016/j.fusengdes.2024.114605","DOIUrl":null,"url":null,"abstract":"<div><p>The Breeding Blanket (BB) is a crucial component in the EU DEMO Fusion Reactor. It has three main important functions: ensuring the thermal power deposition and consequent efficient extraction to achieve a positive net electrical power generation, guaranteeing adequate radiation shielding for personnel and sensible devices working in the Plant, and self-production of enough Tritium to fulfill the reactor self-sufficiency. In past studies, four blanket concepts have been investigated to support achieving these goals. Breeding blanket designs primarily revolve around lithium-containing ceramics, focusing on lithium-orthosilicate and lithium-lead. During the pre-conceptual phase, two blanket options were selected as driven concepts: HCPB (Helium-Cooled Pebble Bed) and WCLL (Water-Cooled Lithium Lead). The HCPB concept employs lithium orthosilicate ceramic pebble beds with lithium titanium oxide as the breeding material. Hexagonal blocks with Be12Ti are positioned around the breeding material tubes and act as the neutron multiplier. In the case of the WCLL concept, LiPb is used as both the breeding material and the neutron multiplier.</p><p>Safety is a top priority in the EU DEMO project, and the approach to evaluating potential activities and doses to workers and the environment reflects this commitment. This study presents neutron flux and specific activity calculations for the EU DEMO breeding materials. The MCNP6 (Monte Carlo N-Particles) was harnessed to estimate neutron spectra in the blanket's breeding material, while the FISPACT-II code was meticulously employed for activation calculations. The nuclear data libraries FENDL 3.2 and TENDL - 2017 were used for transport and activation calculations, respectively, ensuring the highest level of accuracy and reliability in our findings.</p></div>","PeriodicalId":55133,"journal":{"name":"Fusion Engineering and Design","volume":null,"pages":null},"PeriodicalIF":1.9000,"publicationDate":"2024-07-24","publicationTypes":"Journal Article","fieldsOfStudy":null,"isOpenAccess":false,"openAccessPdf":"","citationCount":"0","resultStr":"{\"title\":\"Evaluation of the breeding material activation and radionuclide inventory analysis for EU DEMO\",\"authors\":\"\",\"doi\":\"10.1016/j.fusengdes.2024.114605\",\"DOIUrl\":null,\"url\":null,\"abstract\":\"<div><p>The Breeding Blanket (BB) is a crucial component in the EU DEMO Fusion Reactor. It has three main important functions: ensuring the thermal power deposition and consequent efficient extraction to achieve a positive net electrical power generation, guaranteeing adequate radiation shielding for personnel and sensible devices working in the Plant, and self-production of enough Tritium to fulfill the reactor self-sufficiency. In past studies, four blanket concepts have been investigated to support achieving these goals. Breeding blanket designs primarily revolve around lithium-containing ceramics, focusing on lithium-orthosilicate and lithium-lead. During the pre-conceptual phase, two blanket options were selected as driven concepts: HCPB (Helium-Cooled Pebble Bed) and WCLL (Water-Cooled Lithium Lead). The HCPB concept employs lithium orthosilicate ceramic pebble beds with lithium titanium oxide as the breeding material. Hexagonal blocks with Be12Ti are positioned around the breeding material tubes and act as the neutron multiplier. In the case of the WCLL concept, LiPb is used as both the breeding material and the neutron multiplier.</p><p>Safety is a top priority in the EU DEMO project, and the approach to evaluating potential activities and doses to workers and the environment reflects this commitment. This study presents neutron flux and specific activity calculations for the EU DEMO breeding materials. The MCNP6 (Monte Carlo N-Particles) was harnessed to estimate neutron spectra in the blanket's breeding material, while the FISPACT-II code was meticulously employed for activation calculations. The nuclear data libraries FENDL 3.2 and TENDL - 2017 were used for transport and activation calculations, respectively, ensuring the highest level of accuracy and reliability in our findings.</p></div>\",\"PeriodicalId\":55133,\"journal\":{\"name\":\"Fusion Engineering and Design\",\"volume\":null,\"pages\":null},\"PeriodicalIF\":1.9000,\"publicationDate\":\"2024-07-24\",\"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/S0920379624004563\",\"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/S0920379624004563","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

育种毯(BB)是欧盟 DEMO 聚变反应堆的关键部件。它有三个主要的重要功能:确保热功率沉积和随后的有效提取,以实现正净发电量;确保为在核电厂工作的人员和敏感设备提供足够的辐射屏蔽;以及自行生产足够的氚,以实现反应堆的自给自足。在过去的研究中,已经对四种毯式概念进行了调查,以支持实现这些目标。育种毯设计主要围绕含锂陶瓷,重点是锂-正硅酸盐和锂-铅。在预概念阶段,有两种毯子方案被选为驱动概念:HCPB(氦冷却卵石床)和 WCLL(水冷锂铅)。HCPB 概念采用了以锂钛氧化物为孕育材料的正硅酸锂陶瓷卵石床。含有 Be12Ti 的六角形块被放置在孕育材料管周围,充当中子倍增器。在 WCLL 概念中,锂铅既用作孕育材料,也用作中子倍增器。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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
Evaluation of the breeding material activation and radionuclide inventory analysis for EU DEMO

The Breeding Blanket (BB) is a crucial component in the EU DEMO Fusion Reactor. It has three main important functions: ensuring the thermal power deposition and consequent efficient extraction to achieve a positive net electrical power generation, guaranteeing adequate radiation shielding for personnel and sensible devices working in the Plant, and self-production of enough Tritium to fulfill the reactor self-sufficiency. In past studies, four blanket concepts have been investigated to support achieving these goals. Breeding blanket designs primarily revolve around lithium-containing ceramics, focusing on lithium-orthosilicate and lithium-lead. During the pre-conceptual phase, two blanket options were selected as driven concepts: HCPB (Helium-Cooled Pebble Bed) and WCLL (Water-Cooled Lithium Lead). The HCPB concept employs lithium orthosilicate ceramic pebble beds with lithium titanium oxide as the breeding material. Hexagonal blocks with Be12Ti are positioned around the breeding material tubes and act as the neutron multiplier. In the case of the WCLL concept, LiPb is used as both the breeding material and the neutron multiplier.

Safety is a top priority in the EU DEMO project, and the approach to evaluating potential activities and doses to workers and the environment reflects this commitment. This study presents neutron flux and specific activity calculations for the EU DEMO breeding materials. The MCNP6 (Monte Carlo N-Particles) was harnessed to estimate neutron spectra in the blanket's breeding material, while the FISPACT-II code was meticulously employed for activation calculations. The nuclear data libraries FENDL 3.2 and TENDL - 2017 were used for transport and activation calculations, respectively, ensuring the highest level of accuracy and reliability in our findings.

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.
期刊最新文献
On the fabrication of ultrafine-grained potassium-doped tungsten: Mechanical milling and spark plasma sintering of K-doped W powder prepared by evaporation-condensation method X-ray imaging crystal spectrometer (XICS) diagnostic on the HL-3 tokamak The energy output equilibrium scheme with intermediate energy storage for tokamak fusion power plant Measurement of the mechanical vibration and its impact on the magnetic diagnostics in the J-TEXT tokamak Overview of the TCV digital real-time plasma control system and its applications
×
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