Review of blanket designs for advanced fusion reactors

Review of blanket designs for advanced fusion reactors
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DOI:
10.1016/j.fusengdes.2008.07.039
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发表时间:
2008-12
影响因子:
1.7
通讯作者:
T. Ihli;T. K. Basu;L. Giancarli;S. Konishi;S. Malang;F. Najmabadi;S. Nishio;A. Raffray;C. Rao;A. Sagara;Yucheng Wu
T. Ihli;T. K. Basu;L. Giancarli;S. Konishi;S. Malang;F. Najmabadi;S. Nishio;A. Raffray;C. Rao;A. Sagara;Yucheng Wu
中科院分区:
工程技术3区
文献类型:
--
作者:
T. Ihli;T. K. Basu;L. Giancarli;S. Konishi;S. Malang;F. Najmabadi;S. Nishio;A. Raffray;C. Rao;A. Sagara;Yucheng Wu

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在反应堆中由聚变产生的功率的主要部分被围绕等离子体的包层中的中子慢化捕获。因此,核聚变工厂的效率主要取决于从中子中发电或制氢的技术。本文讨论的主要包层概念是先进的陶瓷增殖反应堆概念,双冷却剂包层以及自冷却液态金属和Flibe包层。讨论的两个重要问题是:(一)我们能否就最有希望的概念得出一个底线结论?(ii)为了确定通向先进聚变反应堆的可行路线,独立于个别设计和布局建议需要解决的共同问题是什么?就陶瓷增殖反应堆概念而言,从长远来看,一个关键问题可能是限制铍作为世界来源和可实现温度水平方面的考虑倍增器。对于液态金属覆盖层,已经开发了有吸引力的长期愿景,但对于容器内覆盖层技术和相应的子系统也存在重大的技术挑战。本文提出了一个战略性的结论,来自先进聚变反应堆的包层设计的审查。
The dominating fraction of the power generated by fusion in the reactor is captured by neutron moderation in the blanket surrounding the plasma. From this, the efficiency of the fusion plant is predominated by the technologies applied to make electricity or hydrogen from the neutrons. The main blanket concepts addressed in this paper are advanced ceramic breeder concepts, dual coolant blankets as well as self-cooled liquid metal and Flibe blankets. Two important questions that are addressed are: (i) Can we draw a bottom line conclusion on the most promising concept(s)? (ii) What are the common issues to be resolved independently from individual design and layout proposals to define a feasible route towards advanced fusion reactors? For ceramic breeder concepts, a key issue in the long term could be the limitation of beryllium as the considered multiplier in terms of world sources and achievable temperature levels. For liquid metal blankets, attractive long-term visions have been developed but major technological challenges also exist for the in-vessel blanket technology and the corresponding sub-systems. The paper proposes a strategic conclusion derived from the review of blanket designs for advanced fusion reactors.