Vacuum hot-pressed beryllium and TiC dispersion strengthened tungsten alloy developments for ITER and future fusion reactors

Vacuum hot-pressed beryllium and TiC dispersion strengthened tungsten alloy developments for ITER and future fusion reactors
复制标题

DOI:
10.1016/j.jnucmat.2013.04.088
复制
发表时间:
2013-11
影响因子:
3.1
通讯作者:
Xiang Liu;Jiming Chen;Y. Lian;Jihong Wu;Zengyu Xu;Nian-man Zhang;Q. Wang;Xu Duan;Zhanhong Wang;J. Zhong
Xiang Liu;Jiming Chen;Y. Lian;Jihong Wu;Zengyu Xu;Nian-man Zhang;Q. Wang;Xu Duan;Zhanhong Wang;J. Zhong
中科院分区:
工程技术2区
文献类型:
--
作者:
Xiang Liu;Jiming Chen;Y. Lian;Jihong Wu;Zengyu Xu;Nian-man Zhang;Q. Wang;Xu Duan;Zhanhong Wang;J. Zhong

文献摘要

被引文献

相似文献

选择铍和钨分别作为ITER第一壁(FW)和分流室的等离子体面材料。中国作为ITER的参与者,将与欧盟和俄罗斯共同承担ITER第一墙模型的制造任务。因此,中国开发了ITER级铍,并获得了一种具有物理、热机械性能和高热流密度性能的真空热压(VHP)铍CN-G01,其性能与ITER的参考级美国S-65C级铍相当。因此,CN-G01铍已被接受作为ITER-FW毯的装甲材料。此外,还研究了对钨进行TiC弥散强化改性的方法,研制出TiC含量为0.1 wt.%的W-TiC合金。表面硬度和再结晶测量表明其再结晶温度约为1773 K。用1.7 keV能量的氘离子辐照0.5 ~ 5 × 1018D/cm2,测定了纯钨和TiC合金的氘保留和热脱附行为;在573 K附近有一个主解吸峰,纯钨和钨合金的解吸峰无显著差异。钨合金的进一步表征正在进行中。
Beryllium and tungsten have been selected as the plasma facing materials of the ITER first wall (FW) and divertor chamber, respectively. China, as a participant in ITER, will share the manufacturing tasks of ITER first-wall mockups with the European Union and Russia. Therefore ITER-grade beryllium has been developed in China and a kind of vacuum hot-pressed (VHP) beryllium, CN-G01, was characterized for both physical, and thermo-mechanical properties and high heat flux performance, which indicated an equivalent performance to U.S. grade S-65C beryllium, a reference grade beryllium of ITER. Consequently CN-G01 beryllium has been accepted as the armor material of ITER-FW blankets. In addition, a modification of tungsten by TiC dispersion strengthening was investigated and a W–TiC alloy with TiC content of 0.1 wt.% has been developed. Both surface hardness and recrystallization measurements indicate its re-crystallization temperature approximately at 1773 K. Deuterium retention and thermal desorption behaviors of pure tungsten and the TiC alloy were also measured by deuterium ion irradiation of 1.7 keV energy to the fluence of 0.5–5 × 1018D/cm2; a main desorption peak at around 573 K was found and no significant difference was observed between pure tungsten and the tungsten alloy. Further characterization of the tungsten alloy is in progress.