Exploring the engineering limit of heat flux of a W/RAFM divertor target for fusion reactors
Exploring the engineering limit of heat flux of a W/RAFM divertor target for fusion reactors
复制标题
探索聚变反应堆 W/RAFM 偏滤器靶的热通量工程极限
DOI：
10.1088/1741-4326/aabb64
复制
发表时间：
2018-04
期刊：
影响因子：
3.3
通讯作者：
Liu P
中科院分区：
文献类型：
--
作者：
Mao X;Fursdon M;Chang X B;Zhang J W;Liu P;Ellwood G;Qian X Y;Qin S J;Peng X B;Barrett T R;Liu P
聚变反应堆偏滤器面向等离子体的组件(PFC)的设计和研制是聚变能源商业化道路上众多具有挑战性的问题之一。偏滤器燃料电池预计将在10兆瓦m−2的范围内排放稳态热负荷，同时将其结构中的温度和热机械应力保持在允许的限度内。针对ITER(国际热核实验堆)，提出了水冷W/CuCrZr偏滤器PFC概念。然而，这一概念不一定能用于未来的聚变反应堆，主要是因为中子辐射剂量将至少高出一个数量级，导致有限的热机械性能和相当多的活性废物产品。在本研究中，采用低活化铁素体-马氏体钢作为散热管，设计了一种水冷偏滤器，其冷却条件类似于压水堆(压力为15.5Mpa，速度为10-20m S−1，温度为300℃)。PFC由许多矩形钨瓷砖组成，每一块都有一个内部圆形孔(即所谓的单块)，连接到带有铜层的RAFM钢管上。对PFC的热力学性能进行了详细的研究。利用已发表的关联式计算了RAFM管内表面与水之间的换热系数。在目标排热负荷为10 mW m−2的情况下，通过有限元热分析优化了结构的几何参数和水流速度，以达到结构中可接受的温度。在此热负荷和优化后的热设计参数下，通过力学分析进一步对结构进行了评估。我们发现在此条件下，RAFM钢管经历了循环塑性，并且不符合一般的线弹性棘轮(3Sm)规则。尽管如此，所设计的W/RAFM偏滤器PFU可以承受10兆瓦m−2热负荷，尽管根据原型或试验反应堆的预期运行方案，其疲劳寿命约为0.55年。该研究拓展了对基于RAFM钢管结构的偏滤器技术极限的认识。
The design and development of a fusion reactor divertor plasma facing component (PFC) is one of the many challenging issues on the road to commercial use of fusion energy. The divertor PFC is expected to exhaust steady state heat loads in the region of 10 MW m−2 while keeping temperatures and thermo-mechanical stresses in its structure within the allowable limits. For ITER (International Thermo-Nuclear Experimental Reactor) a water cooled W/CuCrZr divertor PFC concept has been developed. However, this concept is not necessarily assured for use in future fusion reactors mainly because the neutron radiation dose would be at least an order magnitude higher, resulting in limited thermo-mechanical performance and considerably more activated waste products. In the present study, a water cooled divertor PFC using reduced activation ferritic-martensitic (RAFM) steel as the heat sink pipe has been designed with pressurised water reactor-like cooling conditions (pressure of 15.5 MPa, velocity of 10–20 m s−1 and temperature of 300 °C). The PFC is made up of a number of rectangular tungsten tiles, each with an inner circular hole (so-called monoblocks), joined onto a RAFM steel pipe with copper interlayers. The thermo-mechanical performance of the PFC has been studied in detail. The heat transfer coefficient between the RAFM pipe inner surface and the water was calculated using published correlations. Geometric parameters and water velocity were optimized with finite element (FE) thermal analysis, to achieve acceptable temperatures in the structure given the target exhaust heat load of 10 MW m−2. Under this heat load and the optimised thermal design parameters, the structure of the PFC was further assessed by mechanical analysis. We find that under these conditions the RAFM steel pipe experiences cyclic plasticity, and fails the common linear elastic ratchetting (3 Sm) rule. Nevertheless, the designed W/RAFM divertor PFU can withstand 10 MW m−2 heat load, albeit with a fatigue life of approximately 0.55 years based on the expected operation scenario of a prototype or test reactor. This study extends the state of knowledge of the technological limit of a divertor based on a RAFM steel pipe structure.
登录
查看更多内容
影响因子：
1.7
作者：
F. Crescenzi;C. Bachmann;M. Richou;S. Roccella;E. Visca;J. You
通讯作者：
F. Crescenzi;C. Bachmann;M. Richou;S. Roccella;E. Visca;J. You
影响因子：
6.4
作者：
Namkyu Lee;B. Kim;Taehwan Kim;Ji-Yeul Bae;H. Cho
通讯作者：
Namkyu Lee;B. Kim;Taehwan Kim;Ji-Yeul Bae;H. Cho
影响因子：
1.7
作者：
J. Boscary;M. Araki;J. Schlosser;M. Akiba;F. Escourbiac
通讯作者：
J. Boscary;M. Araki;J. Schlosser;M. Akiba;F. Escourbiac
DOI：
10.1109/sofe.2013.6635311
发表时间：
2013-06
期刊：
2013 IEEE 25th Symposium on Fusion Engineering (SOFE)
影响因子：
--
作者：
B. Wan;S. Ding;J. Qian;Guoqiang Li;B. Xiao;Guosheng Xu
通讯作者：
B. Wan;S. Ding;J. Qian;Guoqiang Li;B. Xiao;Guosheng Xu
影响因子：
3.3
作者：
P. Norajitra;R. Giniyatulin;T. Ihli;G. Janeschitz;P. Karditsas;W. Krauss;R. Krüssmann;V. Kuznetsov-V.-Kuz
通讯作者：
P. Norajitra;R. Giniyatulin;T. Ihli;G. Janeschitz;P. Karditsas;W. Krauss;R. Krüssmann;V. Kuznetsov-V.-Kuz