Shielding design and neutronics calculation of the GDT based fusion neutron source ALIANCE
文献类型：期刊论文
| 作者 | Yang, Wenjie2,3; Zeng, Qiusun2 ; Chen, Chao2,3; Chen, Zhibin2; Song, Jun2,3; Wang, Zhen2; Yu, Jie2; Yakovlev, Dmitry1; Prikhodko, Vadim1,4
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| 刊名 | FUSION ENGINEERING AND DESIGN
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| 出版日期 | 2021-03-01 |
| 卷号 | 164 |
| 关键词 | Gas dynamic trap Fusion neutron source Shielding optimization Specific activity |
| ISSN号 | 0920-3796 |
| DOI | 10.1016/j.fusengdes.2020.112221 |
| 通讯作者 | Zeng, Qiusun(qiusun.zeng@inest.cas.cn) |
| 英文摘要 | This paper presents the high flux neutron shielding design and extensive neutronics calculations of GDT based fusion neutron source ALIANCE. Neutron distribution of ALIANCE is strongly inhomogeneous along the axis: significant portion of the neutron flux is generated near the two mirrors, while the rest of it is spread over the remaining central volume of plasma. The shielding design includes 40 cm stainless steel as the main shielding layer and an additional 5 cm tungsten carbide shielding layer at mirror plugs to protect superconducting coils from neutron damage and reduce nuclear heating. The simulations have been carried out by using Monte Carlo transport code SuperMC with nuclear data library FENDL 3.1. Results show that the nuclear heating on the mirror coils can be reduced by more than two thirds with additional tungsten carbide shield, and fast neutron fluence by 30 %. The highest nuclear heating and the highest fast neutron fluence zones are located at the mirror coils, and the values are about 300 W/m(3) and 9 x 10(18) n/cm(2) respectively, which meets the threshold of ITER superconducting coils. The specific activities of shielding layers are of order of 10(12) Bq/kg. The structural materials? specific activities will decrease to 4 x 10(11) Bq/kg in one year after shutdown, and their decay heat will quickly drop below 2 kW/m(3) after one day. Besides, all the structural materials of ALIANCE can be recycled by different recycling technologies. The modeling and calculations reported in this paper will be beneficial for the pre-conceptual engineering design of ALIANCE. |
| 资助项目 | IAEA Coordinate Research Project[F1301822776] ; Anhui Provincial Natural Science Foundation[202004b11020032] ; Anhui Provincial Natural Science Foundation[1908085MA17] ; ChinaUkraine science and technology cooperation project[CU0324] |
| WOS研究方向 | Nuclear Science & Technology |
| 语种 | 英语 |
| WOS记录号 | WOS:000631331800002 |
| 出版者 | ELSEVIER SCIENCE SA |
| 资助机构 | IAEA Coordinate Research Project ; Anhui Provincial Natural Science Foundation ; ChinaUkraine science and technology cooperation project |
| 源URL | [http://ir.hfcas.ac.cn:8080/handle/334002/120961]  |
| 专题 | 中国科学院合肥物质科学研究院 |
| 通讯作者 | Zeng, Qiusun |
| 作者单位 | 1.Russian Acad Sci, Siberian Branch, Budker Inst Nucl Phys, Novosibirsk 630090, Russia 2.Chinese Acad Sci, Hefei Inst Phys Sci, Inst Nucl Energy Safety Technol, Hefei 230031, Anhui, Peoples R China 3.Univ Sci & Technol China, Hefei 230027, Anhui, Peoples R China 4.Novosibirsk State Univ, Novosibirsk 630090, Russia |
| 推荐引用方式 GB/T 7714 | Yang, Wenjie,Zeng, Qiusun,Chen, Chao,et al. Shielding design and neutronics calculation of the GDT based fusion neutron source ALIANCE[J]. FUSION ENGINEERING AND DESIGN,2021,164. |
| APA | Yang, Wenjie.,Zeng, Qiusun.,Chen, Chao.,Chen, Zhibin.,Song, Jun.,...&Prikhodko, Vadim.(2021).Shielding design and neutronics calculation of the GDT based fusion neutron source ALIANCE.FUSION ENGINEERING AND DESIGN,164. |
| MLA | Yang, Wenjie,et al."Shielding design and neutronics calculation of the GDT based fusion neutron source ALIANCE".FUSION ENGINEERING AND DESIGN 164(2021). |
入库方式： OAI收割
来源：合肥物质科学研究院
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