在欧盟DEMO概念前设计阶段设计DEMO驱动毯系统的进展:概述、挑战和机遇

IF 0.5 Q4 NUCLEAR SCIENCE & TECHNOLOGY Journal of Nuclear Engineering and Radiation Science Pub Date : 2023-08-03 DOI:10.3390/jne4030037
F. Hernández, P. Arena, L. Boccaccini, I. Cristescu, A. Del Nevo, Pierre Sardain, G. Spagnuolo, M. Utili, A. Venturini, Guangming Zhou
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引用次数: 0

摘要

在欧洲聚变联盟的框架下,欧盟在2014-2020年期间进行了示范反应堆(DEMO)的概念前设计(PCD)阶段。DEMO设计的当前策略是通过扮演BB的“组件测试设施”的角色,弥合ITER和商业聚变发电厂(FPP)之间的繁殖毯(BB)技术差距。在这一战略中,所谓的驱动毯,具有几乎完全的船内表面覆盖,旨在通过相当传统的技术和/或操作参数实现高水平的利益相关者对氚自给自足和净电力生产的电力提取的要求,而先进毯(或其中几个)的目标是在有限的覆盖范围内展示商业FPP所必需的功能。目前,欧盟DEMO正在研究两种候选驱动毯,即水冷锂铅和氦冷卵石床育种毯概念。PCD阶段的特点不仅在于BB系统本身的详细设计,还在于它们在DEMO中的整体集成,根据驾驶员毯子的想法优先考虑近期解决方案。本文总结了两种BB驱动层候选材料在PCD阶段的状态,包括相应的氚提取和去除(TER)系统,强调了主要成就和经验教训,揭示了突出的关键系统设计和研发挑战,并提出了在2021年开始的概念设计(CD)阶段解决这些风险的确定机会。
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Advancements in Designing the DEMO Driver Blanket System at the EU DEMO Pre-Conceptual Design Phase: Overview, Challenges and Opportunities
The EU conducted the pre-conceptual design (PCD) phase of the demonstration reactor (DEMO) during 2014–2020 under the framework of the EUROfusion consortium. The current strategy of DEMO design is to bridge the breeding blanket (BB) technology gaps between ITER and a commercial fusion power plant (FPP) by playing the role of a “Component Test Facility” for the BB. Within this strategy, a so-called driver blanket, with nearly full in-vessel surface coverage, will aim at achieving high-level stakeholder requirements of tritium self-sufficiency and power extraction for net electricity production with rather conventional technology and/or operational parameters, while an advanced blanket (or several of them) will aim at demonstrating, with limited coverage, features that are deemed necessary for a commercial FPP. Currently, two driver blanket candidates are being investigated for the EU DEMO, namely the water-cooled lithium lead and the helium-cooled pebble bed breeding blanket concepts. The PCD phase has been characterized not only by the detailed design of the BB systems themselves, but also by their holistic integration in DEMO, prioritizing near-term solutions, in accordance with the idea of a driver blanket. This paper summarizes the status for both BB driver blanket candidates at the end of the PCD phase, including their corresponding tritium extraction and removal (TER) systems, underlining the main achievements and lessons learned, exposing outstanding key system design and R&D challenges and presenting identified opportunities to address those risks during the conceptual design (CD) phase that started in 2021.
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来源期刊
CiteScore
1.30
自引率
0.00%
发文量
56
期刊介绍: The Journal of Nuclear Engineering and Radiation Science is ASME’s latest title within the energy sector. The publication is for specialists in the nuclear/power engineering areas of industry, academia, and government.
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