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| Transition toward thorium fuel cycle in a molten salt reactor by using plutonium | |
| Cui, DY; Xia, SP; Li, XX; Cai, XZ; Chen, JG | |
| 2017 | |
| Source Publication | NUCLEAR SCIENCE AND TECHNIQUES
 |
| ISSN | 1001-8042 |
| Volume | 28Issue:10Pages:- |
| Subtype | 期刊论文 |
| Abstract | The molten salt reactor (MSR), as one of the Generation IV advanced nuclear systems, has attracted a worldwide interest due to its excellent performances in safety, economics, sustainability, and proliferation resistance. The aim of this work is to provide and evaluate possible solutions to fissile U-233 production and further the fuel transition to thorium fuel cycle in a thermal MSR by using plutonium partitioned from light water reactors spent fuel. By using an in-house developed tool, a breeding and burning (B&B) scenario is first introduced and analyzed from the aspects of the evolution of main nuclides, net U-233 production, spectrum shift, and temperature feedback coefficient. It can be concluded that such a Th/Pu to Th = U-233 transition can be accomplished by employing a relatively fast fuel reprocessing with a cycle time less than 60 days. At the equilibrium state, the reactor can achieve a conversion ratio of about 0.996 for the 60-day reprocessing period (RP) case and about 1.047 for the 10-day RP case. The results also show that it is difficult to accomplish such a fuel transition with limited reprocessing (RP is 180 days), and the reactor operates as a converter and burns the plutonium with the help of thorium. Meanwhile, a prebreeding and burning (PB&B) scenario is also analyzed briefly with respect to the net U-233 production and evolution of main nuclides. One can find that it is more efficient to produce U-233 under this scenario, resulting in a double time varying from about 1.96 years for the 10-day RP case to about 6.15 years for the 180-day RP case. |
| Keyword | Msr Advantages |
| DOI | 10.1007/s41365-017-0303-y |
| Indexed By | SCI |
| WOS Keyword | MSR ; ADVANTAGES |
| Language | 英语 |
| WOS ID | WOS:000411149700015 |
| Citation statistics | |
| Document Type | 期刊论文 |
| Identifier | http://ir.sinap.ac.cn/handle/331007/28881 |
| Collection | 中科院上海应用物理研究所2011-2019年 |
| Recommended Citation GB/T 7714 | Cui, DY,Xia, SP,Li, XX,et al. Transition toward thorium fuel cycle in a molten salt reactor by using plutonium[J]. NUCLEAR SCIENCE AND TECHNIQUES,2017,28(10):-. |
| APA | Cui, DY,Xia, SP,Li, XX,Cai, XZ,&Chen, JG.(2017).Transition toward thorium fuel cycle in a molten salt reactor by using plutonium.NUCLEAR SCIENCE AND TECHNIQUES,28(10),-. |
| MLA | Cui, DY,et al."Transition toward thorium fuel cycle in a molten salt reactor by using plutonium".NUCLEAR SCIENCE AND TECHNIQUES 28.10(2017):-. |
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| File Name/Size | DocType | Version | Access | License | ||
| Transition toward th（1893KB） | 期刊论文 | 作者接受稿 | 开放获取 | CC BY-NC-SA | View Download | |
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