Development of a system level code for tritium transport analysis of the WCCB blanket for CFETR
文献类型：期刊论文
| 作者 | Huang, Kai2; Zhao, Xueli2,3; Ma, Xuebin1; Liu, Songlin2
|
| 刊名 | FUSION ENGINEERING AND DESIGN
 |
| 出版日期 | 2020-04-01 |
| 卷号 | 153 |
| 关键词 | Tritium transport System level WCCB blanket CFETR |
| ISSN号 | 0920-3796 |
| DOI | 10.1016/j.fusengdes.2020.111501 |
| 通讯作者 | Huang, Kai(huangkai@ipp.ac.cn) |
| 英文摘要 | Tritium is the fuel for the future D-T magnetic-confined fusion devices such as the China Fusion Engineering Test Reactor (CFETR). Accurate assessment of the tritium transport behaviors within the reactor is essential to the fulfillment of fuel self-sustainability and public safety concerns. Due to the radioactive nature of this hydrogen isotope, numerical simulations are often used as a more convenient and realizable approach to provide data and insights regarding the evaluation of overall tritium distribution, permeation, and inventory. In this work, we developed an in-house tritium transport analysis code for the water-cooled ceramic breeder (WCCB) blanket for CFETR at the system level. The math-physics models applied incorporate the multi-physical processes required in the full functional description of macroscopic tritium transport. The code extends the capability of the existing, pioneering OD codes in this area to take care of the varying configurations of different blanket modules within a fusion reactor. The code developed is applied as a first attempt to evaluate the overall tritium transport behaviors in the WCCB blanket system for CFETR. Preliminary simulation results are reported and discussed. It suggests that the in-homogeneity effect introduced by the geometric and material configurations varying across blanket modules can bring a marked impact on the tritium transport performance, thus is desirable to be taken into account in system-level codes to improve the prediction results. |
| WOS关键词 | BREEDER BLANKET ; MODEL ; PERMEATION ; HCLL |
| 资助项目 | National Key R&D Program of China[2017YFE0300502] ; National Natural Science Foundation of China[11775256] |
| WOS研究方向 | Nuclear Science & Technology |
| 语种 | 英语 |
| WOS记录号 | WOS:000518408500010 |
| 出版者 | ELSEVIER SCIENCE SA |
| 资助机构 | National Key R&D Program of China ; National Natural Science Foundation of China |
| 源URL | [http://ir.hfcas.ac.cn:8080/handle/334002/103791]  |
| 专题 | 中国科学院合肥物质科学研究院 |
| 通讯作者 | Huang, Kai |
| 作者单位 | 1.Shenzhen Univ, Adv Energy Res Ctr, Shenzhen 518060, Peoples R China 2.Chinese Acad Sci, Inst Plasma Phys, Hefei 230031, Anhui, Peoples R China 3.Univ Sci & Technol China, Hefei 230037, Anhui, Peoples R China |
| 推荐引用方式 GB/T 7714 | Huang, Kai,Zhao, Xueli,Ma, Xuebin,et al. Development of a system level code for tritium transport analysis of the WCCB blanket for CFETR[J]. FUSION ENGINEERING AND DESIGN,2020,153. |
| APA | Huang, Kai,Zhao, Xueli,Ma, Xuebin,&Liu, Songlin.(2020).Development of a system level code for tritium transport analysis of the WCCB blanket for CFETR.FUSION ENGINEERING AND DESIGN,153. |
| MLA | Huang, Kai,et al."Development of a system level code for tritium transport analysis of the WCCB blanket for CFETR".FUSION ENGINEERING AND DESIGN 153(2020). |
入库方式： OAI收割
来源：合肥物质科学研究院
浏览0
下载0
收藏0
其他版本
除非特别说明，本系统中所有内容都受版权保护，并保留所有权利。