| Numerical approach to study the thermal-hydraulic characteristics of Reactor Vessel Cooling system in sodium-cooled fast reactors | |
| Song, Ping; Zhang, Dalin; Feng, Tangtao; Wang, Shibao; Chen, Jing; Wang, Xin'an; Xue, Xiuli; Zhang, Yapei; Wang, Mingjun; Qiu, Suizheng | |
| 刊名 | PROGRESS IN NUCLEAR ENERGY
 |
| 2019 | |
| 卷号 | Vol.110页码:213-223 |
| 关键词 | Reactor vessel cooling system Code development Sodium-cooled fast reactor Sensitivity analysis |
| ISSN号 | 0149-1970 |
| URL标识 | 查看原文 |
| 公开日期 | [db:dc_date_available] |
| 内容类型 | 期刊论文 |
| URI标识 | http://www.corc.org.cn/handle/1471x/4618140 |
| 专题 | 湖南大学 |
| 作者单位 | 1.Xi An Jiao Tong Univ, State Key Lab Multiphase Flow Power Engn, Sch Nucl Sci & Technol, 28 Xianning West Rd, Xian 710049, Shaanxi, Peoples R China 2.China Inst Atom Energy, Beijing, Peoples R China |
| 推荐引用方式 GB/T 7714 | Song, Ping,Zhang, Dalin,Feng, Tangtao,et al. Numerical approach to study the thermal-hydraulic characteristics of Reactor Vessel Cooling system in sodium-cooled fast reactors[J]. PROGRESS IN NUCLEAR ENERGY,2019,Vol.110:213-223. |
| APA | Song, Ping.,Zhang, Dalin.,Feng, Tangtao.,Wang, Shibao.,Chen, Jing.,...&Qiu, Suizheng.(2019).Numerical approach to study the thermal-hydraulic characteristics of Reactor Vessel Cooling system in sodium-cooled fast reactors.PROGRESS IN NUCLEAR ENERGY,Vol.110,213-223. |
| MLA | Song, Ping,et al."Numerical approach to study the thermal-hydraulic characteristics of Reactor Vessel Cooling system in sodium-cooled fast reactors".PROGRESS IN NUCLEAR ENERGY Vol.110(2019):213-223. |
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