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Japanese activities of the R&D on silicon carbide composites in the broader approach period and beyond
Journal of Nuclear Materials ( IF 3.1 ) Pub Date : 2018-05-19 , DOI: 10.1016/j.jnucmat.2018.05.045
Takashi Nozawa , Kazumi Ozawa , ChangHo Park , Joon-Soo Park , Akira Kohyama , Akira Hasegawa , Shuhei Nogami , Tatsuya Hinoki , Sosuke Kondo , Toyohiko Yano , Tamaki Shibayama , Bun Tsuchiya , Tatsuo Shikama , Shinji Nagata , Teruya Tanaka , Hirotomo Iwakiri , Yasushi Yamamoto , Satoshi Konishi , Ryuta Kasada , Masatoshi Kondo , Tomoaki Kunugi , Takehiko Yokomine , Yoshitaka Ueki , Nariaki Okubo , Tomitsugu Taguchi , Hiroyasu Tanigawa

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.



中文翻译:

在更广泛的时期内及以后,日本在碳化硅复合材料方面的研发活动

在日本和欧盟之间针对熔合DEMO的更广泛方法(BA)活动下进行的SiC / SiC复合材料的研发,建立了机械(Task-1)和物理/化学(Task-2)性能的基本数据库,其主要目标是SiC / SiC复合材料作为功能性结构的应用,可用于双重冷却剂繁殖毯概念。本文旨在总结日本过去10年的研发活动,并提供用于DEMO设计的关键交付物。在Task-1中,首次展示了良好的蠕变和疲劳耐久性。此外,全面确定了高温下的平面内和层间强度各向异性图。在平行下,SiC材料的辐照效果被专门确定为分析模型的输入参数,以提供辐照引起的残余应力。在任务2中,通过各种辐照源确定了辐射诱导的电导率和指示性辐射诱导的电降解的明显剂量依赖性。此外,还确定了良好的气体限制。此外,首次证明在低于1173 K的温度下持续3000小时没有加速腐蚀。凭借这些成就,建议采用船内组件技术,例如材料腐蚀数据库开发,活性腐蚀产物评估代码开发,用于验证组件关键功能的紧凑模块测试,核聚变测试的技术集成评估, ETC。,

更新日期:2018-05-19
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