Japanese activities of the R&D on silicon carbide composites in the broader approach period and beyond
Japanese activities of the R&D on silicon carbide composites in the broader approach period and beyond
复制标题
R的日本活动
DOI：
10.1016/j.jnucmat.2018.05.045
复制
发表时间：
2018
影响因子：
3.1
通讯作者：
Tanigawa Hiroyasu
中科院分区：
文献类型：
--
作者：
Nozawa Takashi;Ozawa Kazumi;Park ChangHo;Park Joon-Soo;Kohyama Akira;Hasegawa Akira;Nogami Shuhei;Hinoki Tatsuya;Kondo Sosuke;Yano Toyohiko;Shibayama Tamaki;Tsuchiya Bun;Shikama Tatsuo;Nagata Shinji;他10名;Taguchi Tomitsugu;Tanigawa Hiroyasu
在日本和欧盟之间关于聚变DEMO的更广泛方法（BA）活动下的SiC/SiC复合材料的研发开发了机械（任务-1）和物理/化学（任务-2）性能的基础数据库，主要目标是SiC/SiC复合材料作为功能结构应用于双冷却剂增殖包层概念。本文旨在总结日本过去10年的R&D活动，并提供DEMO设计的关键成果。在任务-1中，首次证明了良好的蠕变和疲劳耐久性。此外，全面识别了高温下的面内和层间强度各向异性图。同时，SiC材料的辐照效应被具体确定为分析模型的输入参数，以提供辐照诱导的残余应力。在任务-2中，通过各种辐照源确定了辐射诱导电导率和指示性辐射诱导电降解的明显剂量依赖性。此外，确定了良好的气体密封。此外，首次证明在低于1173 K下持续3000 h没有加速腐蚀。基于这些成果，提出了船舶内构件技术，例如，材料腐蚀数据库开发、活化腐蚀产品评估代码开发、验证组件关键功能的紧凑模块测试、聚变核试验的技术集成评估等，近期应进一步向DEMO方向发展。
The R&D on SiC/SiC composites under the broader approach (BA) activities between Japan and the EU for fusion DEMO developed a fundamental database of mechanical (Task-1) and physical/chemical (Task-2) properties, with a primary target of the application of SiC/SiC composites as functional structure to be used in the dual coolant breeding blanket concept. This paper aims to summarize previous 10-years activities of the R&D of Japan and to provide the key deliverables toward the DEMO design. In Task-1, good creep and fatigue durability were first demonstrated. Besides, in-plane and inter-laminar strength anisotropy maps at elevated temperatures were comprehensively identified. In parallel, the irradiation effects of SiC materials were specifically determined as input parameters of the analytical model to provide for the irradiation-induced residual stresses. In Task-2, the apparent dose-dependence of the radiation-induced electrical conductivity and the indicative radiation-induced electrical degradation was identified by various irradiation sources. In addition, good gas confinement was identified. Furthermore, no accelerated corrosion for duration of 3000 h at below 1173 K was first demonstrated. With these achievements, it is suggested that the in-vessel component technology, e.g., material corrosion database development, activated corrosion product evaluation code development, compact module tests for validation of the key functions of the components, technology integration assessment for fusion nuclear tests, etc., should be further developed toward DEMO in near-term.