WCCB tbm机组结构初步设计

IF 2 3区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Wenhai Guan , Takanori Hirose , Yoshinori Kawamura , Hiroyasu Tanigawa
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引用次数: 0

摘要

本研究提出了水冷陶瓷增殖器(WCCB)测试包层模块(TBM)的初步结构设计,该组件由日本量子科学与技术研究所提出,旨在安装在ITER的赤道端口18号。在ITER负载环境下对WCCB TBM-set进行了局部氚增殖比(TBR)、子模块温度分布和结构完整性评估,完成了初步设计活动的评审。数值分析,包括核和有限元分析,用于评估局部TBR,温度分布,电磁(EM)力,载荷组合和应力性能。结果表明,在维持现有局部TBR的情况下,需要三种冷却能力增强结构来提高倍增器球床区域的冷却能力。EM分析表明,麦克斯韦力将持续作用于WCCB tbm集,无论正常运行或等离子体中断,主要是由于使用铁磁材料。此外,对WCCB TBM机组中为TBM和盾构提供机械支撑的支架的结构完整性进行了荷载组合下的评估。虽然支架目前的性能还不够,但设计修改可能使其满足RCC-MRx中概述的标准。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
Preliminary structural design of WCCB TBM-set
This study presents a preliminary structural design of the water-cooled ceramic breeder (WCCB) Test Blanket Module (TBM)-set, proposed by the Institutes for Quantum Science and Technology in Japan, which is intended for installation in ITER's equatorial port No. 18. The research investigates the local tritium breeding ratio (TBR), the temperature distribution of the submodule, and the structural integrity assessment of the WCCB TBM-set under the ITER load environment to complete the review of the preliminary design activities. Numerical analyses, including nuclear and finite element analyses, are utilized to evaluate local TBR, temperature distribution, electromagnetic (EM) forces, load combinations, and stress performance. The results indicate that three cooling capacity enhancement structures are necessary to improve cooling capacity in the multiplier pebble bed area while maintaining the current local TBR. The EM analysis demonstrates that a Maxwell force will constantly act on the WCCB TBM-set, regardless of normal operation or plasma disruption, primarily due to the use of ferromagnetic materials. Furthermore, the structural integrity of the supporter, which provides mechanical support for the TBM and the shield in the WCCB TBM-set, is evaluated under load combinations. Although the current performance of the supporter is inadequate, design modifications may enable it to meet the criteria outlined in RCC-MRx.
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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.
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