Design and Analysis of Mock-up of CFETR COOL Blanket for Neutronic Experiment

IF 1.9 4区 工程技术 Q1 NUCLEAR SCIENCE & TECHNOLOGY
Qiankun Shao, Qingjun Zhu
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Abstract

The purpose of this study is to design and analysis a neutronic experimental mock-up for supercritical carbon dioxide cooled Lithium-Lead (COOL) blanket of CFETR. The protype of mock-up is the equatorial outboard breeding unit (3# unit) of COOL blanket, which have the largest neutron wall loading. To verify the reliability of neutronic design of COOL blanket, the neutronic property of mock-up should be designed to be consistent with the protype. To facilitate detector layout and component installation, simplifications in radial arrangement of mock-up are necessary. The determined radial layout is arranged as Plasma Facing Component, First Wall, Gap 1, Flow Channel Insert 1 (FCI 1), Breeding Zone (BZ), Flow Channel Insert 2 (FCI 2), Gap 2 and Manifold (MF). And the dimensions of toroidal and poloidal were determined by the extent of neutrons leaking from the edge of mock-up. The determined size of the experimental mock-up is 500 mm (Toroidal)×500 mm (Poloidal)×326 mm (Radial). Ultimately, neutronic property and activation property of the mock-up is analyzed. The calculation results showed that the designed mock-up can be used to carry out neutronic experiment. This work will provide a guideline for design of next stage experiment.

中子实验用CFETR冷毯模型的设计与分析
本研究的目的是设计和分析CFETR超临界二氧化碳冷却锂铅(COOL)包层的中子实验模型。模型的原型是具有最大中子壁负荷的COOL毯的赤道外增殖单元(3#单元)。为了验证冷毯中子设计的可靠性,应设计出与原型相符的实物模型。为了便于探测器布局和元件安装,有必要简化模型的径向排列。确定的径向布局布置为等离子体面向组件、第一壁、间隙1、流道插入1 (FCI 1)、繁殖区(BZ)、流道插入2 (FCI 2)、间隙2和歧管(MF)。环形和极向的尺寸由模型边缘的中子泄漏程度决定。实验模型的确定尺寸为500mm(环形)×500 mm(极向)×326 mm(径向)。最后对模型的中子特性和活化特性进行了分析。计算结果表明,所设计的模型可以用于进行中子实验。本工作将为下一阶段的实验设计提供指导。
本文章由计算机程序翻译,如有差异,请以英文原文为准。
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来源期刊
Journal of Fusion Energy
Journal of Fusion Energy 工程技术-核科学技术
CiteScore
2.20
自引率
0.00%
发文量
24
审稿时长
2.3 months
期刊介绍: The Journal of Fusion Energy features original research contributions and review papers examining and the development and enhancing the knowledge base of thermonuclear fusion as a potential power source. It is designed to serve as a journal of record for the publication of original research results in fundamental and applied physics, applied science and technological development. The journal publishes qualified papers based on peer reviews. This journal also provides a forum for discussing broader policies and strategies that have played, and will continue to play, a crucial role in fusion programs. In keeping with this theme, readers will find articles covering an array of important matters concerning strategy and program direction.
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