Thorium utilization with pebble mixing system in fluoride salt-cooled High Temperature Reactor
文献类型：期刊论文
| 作者 | Zhu, GF; Liu, SJ; Zou, Y; Yan, R; Tan, ML; Kang, XZ; Li, MH; Zhou, B; Dai, Y |
| 刊名 | PROGRESS IN NUCLEAR ENERGY
 |
| 出版日期 | 2019 |
| 卷号 | 114期号:-页码:84—90 |
| 关键词 | URANIA FUEL CORE |
| ISSN号 | 0149-1970 |
| DOI | 10.1016/j.pnucene.2019.02.005 |
| 文献子类 | 期刊论文 |
| 英文摘要 | Mixing system of uranium pebbles and thorium pebbles is compared with thorium blanket system to utilize thorium in Pebble Bed Fluoride Salt-cooled High Temperature Reactor (PB-FHR). A random modeling method is introduced to simulate the pebble mixing system. Cases with different volume fractions of uranium pebbles are researched to find the optimal utilization of uranium and the lower power nonuniformity. It indicates that using thorium in pebble mixing system with 80 vol% uranium pebbles can improve uranium utilization by 10%, while in thorium blanket system it can be increased by 20%. The radial power peak factor in pebble mixing system is about 1.48 while in thorium blanket system is about 1.83. In-pile residence time of thorium pebbles in pebble mixing system is only 4.7 year, while in thorium blanket system is 9 year. Thorium utilization with pebble mixing system in PB-FHR shows a little lower fuel utilization but higher safety and technical feasibility. |
| 语种 | 英语 |
| 源URL | [http://ir.sinap.ac.cn/handle/331007/31878]  |
| 专题 | 上海应用物理研究所_中科院上海应用物理研究所2011-2017年 |
| 作者单位 | Chinese Acad Sci, Shanghai Inst Appl Phys, Shanghai 201800, Peoples R China |
| 推荐引用方式 GB/T 7714 | Zhu, GF,Liu, SJ,Zou, Y,et al. Thorium utilization with pebble mixing system in fluoride salt-cooled High Temperature Reactor[J]. PROGRESS IN NUCLEAR ENERGY,2019,114(-):84—90. |
| APA | Zhu, GF.,Liu, SJ.,Zou, Y.,Yan, R.,Tan, ML.,...&Dai, Y.(2019).Thorium utilization with pebble mixing system in fluoride salt-cooled High Temperature Reactor.PROGRESS IN NUCLEAR ENERGY,114(-),84—90. |
| MLA | Zhu, GF,et al."Thorium utilization with pebble mixing system in fluoride salt-cooled High Temperature Reactor".PROGRESS IN NUCLEAR ENERGY 114.-(2019):84—90. |
入库方式： OAI收割
来源：上海应用物理研究所
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