Investigation on the Tritium Self-Sufficiency and Neutron Shielding Based on a Water-Cooled Blanket for CFETR at 1.5 GW
文献类型：期刊论文
| 作者 | Li, Jie1,2; Zhang, Jie1 ; Liu, Changle1; Liu, Xiaogang1; Gao, Xiang1
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| 刊名 | IEEE TRANSACTIONS ON PLASMA SCIENCE
 |
| 出版日期 | 2021-10-01 |
| 卷号 | 49 |
| 关键词 | Neutrons Plasmas Solid modeling Inductors Production Optimization Loading China Fusion Engineering Test Reactor (CFETR) neutronics study neutron wall loading (NWL) tritium breeding ratio (TBR) water-cooled ceramic breeder (WCCB) |
| ISSN号 | 0093-3813 |
| DOI | 10.1109/TPS.2021.3110583 |
| 通讯作者 | Zhang, Jie(jzhang@ipp.ac.cn) |
| 英文摘要 | China Fusion Engineering Test Reactor (CFETR) is a new test tokamak device in China, which is to bridge the scientific and technical gaps between ITER and DEMO. One of the main missions of CFETR is to achieve tritium self-sufficiency with a tritium breeding ratio (TBR) of no less than 1.05. In addition, the neutron shielding evaluation is also a significant issue, which could provide a significant reference for the water-cooled ceramic breeder (WCCB) blanket modification and improvements. In this work, a 3-D simplified neutronics model containing the WCCB blanket is developed and the neutronics performance is calculated based on the 1.5 GW fusion power. The nuclear analyses are carried out by the Monte Carlo N-particle (MCNP) transport code, including the TBR, neutron wall loading (NWL), fast neutron flux on inboard side, and nuclear heating deposition on main in-vessel components. It is found that the net TBR reaches 1.23, which meets the condition of tritium self-sufficiency. Moreover, it is found that the peak NWL of inboard and outboard occurs in the equatorial plane. The inboard peak NWL is 1.89 MW/m(2) and the outboard peak NWL is 1.97 MW/m(2). In addition, the fast neutron flux and nuclear heating deposition at the inboard midplane in toroidal field coil (TFC) are obtained. According to the radiation limits of the CFETR TFC referring to ITER, the results show the nuclear responses of the TFC meet the limit criteria. |
| WOS关键词 | BREEDER BLANKET ; PHYSICS |
| 资助项目 | National MCF Energy Research and Development Program[2019YFE03090200] ; National Natural Science Foundation of China[11975230] |
| WOS研究方向 | Physics |
| 语种 | 英语 |
| WOS记录号 | WOS:000707442700029 |
| 出版者 | IEEE-INST ELECTRICAL ELECTRONICS ENGINEERS INC |
| 资助机构 | National MCF Energy Research and Development Program ; National Natural Science Foundation of China |
| 源URL | [http://ir.hfcas.ac.cn:8080/handle/334002/125577]  |
| 专题 | 中国科学院合肥物质科学研究院 |
| 通讯作者 | Zhang, Jie |
| 作者单位 | 1.Chinese Acad Sci, Inst Plasma Phys, Hefei 230026, Peoples R China 2.Univ Sci & Technol China, Sci Isl Branch, Grad Sch, Hefei 230031, Peoples R China |
| 推荐引用方式 GB/T 7714 | Li, Jie,Zhang, Jie,Liu, Changle,et al. Investigation on the Tritium Self-Sufficiency and Neutron Shielding Based on a Water-Cooled Blanket for CFETR at 1.5 GW[J]. IEEE TRANSACTIONS ON PLASMA SCIENCE,2021,49. |
| APA | Li, Jie,Zhang, Jie,Liu, Changle,Liu, Xiaogang,&Gao, Xiang.(2021).Investigation on the Tritium Self-Sufficiency and Neutron Shielding Based on a Water-Cooled Blanket for CFETR at 1.5 GW.IEEE TRANSACTIONS ON PLASMA SCIENCE,49. |
| MLA | Li, Jie,et al."Investigation on the Tritium Self-Sufficiency and Neutron Shielding Based on a Water-Cooled Blanket for CFETR at 1.5 GW".IEEE TRANSACTIONS ON PLASMA SCIENCE 49(2021). |
入库方式： OAI收割
来源：合肥物质科学研究院
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