Analysis of thorium and uranium based nuclear fuel options in Fluoride salt-cooled High-temperature Reactor
文献类型：期刊论文
| 作者 | Li, XX; Cai, XZ; Jiang, DZ; Ma, YW; Huang, JF; Zou, CY; Yu, CG; Han, JL; Chen, JG |
| 刊名 | PROGRESS IN NUCLEAR ENERGY
 |
| 出版日期 | 2015 |
| 卷号 | 78页码:285—290 |
| 关键词 | CYCLES |
| 英文摘要 | In order to utilize thorium in Fluoride salt-cooled High-temperature Reactor (FHR), neutronics analysis for thorium based fuels (U-233 + Th, U-235 + Th and Pu-239 + Th) is carried out in a whole-core model of pebble bed FHR. Uranium (U-239) based fuels with the above three fissile nuclides are also analyzed for comparison. The atomic density of fissile material is kept constant at start-up for the six fuel types. Neutron characteristics including neutron spectrum, effective multiplicity factor (k(eff)), temperature coefficient of reactivity (TCR), conversion ratio (CR) and burnup for the six fuel options are discussed. With the same fissile nuclide, the thorium based fuels have a higher initial k(eff) than the uranium based fuels due to the smaller resonance absorption of Th-232. As for fissile material, U-233 is the best candidate as a driver fuel in thermal and epithermal spectra due to its effective number of fission neutrons (eta). Besides, the Th-232/U-233 fuel can be extended to radioactive waste management benefited from deeper burnup and lower level of radio-toxicity. The FHR core with thermal and epithermal spectra is more suitable for Th-U fuel cycle than U-Pu fuel cycle. These analyses can provide an approach for the further optimizations of thorium utilization in FHR. (C) 2014 Elsevier Ltd. All rights reserved. |
| 收录类别 | SCI |
| 语种 | 英语 |
| 公开日期 | 2015-12-24 |
| 源URL | [http://ir.sinap.ac.cn/handle/331007/24395]  |
| 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 |
| 推荐引用方式 GB/T 7714 | Li, XX,Cai, XZ,Jiang, DZ,et al. Analysis of thorium and uranium based nuclear fuel options in Fluoride salt-cooled High-temperature Reactor[J]. PROGRESS IN NUCLEAR ENERGY,2015,78:285—290. |
| APA | Li, XX.,Cai, XZ.,Jiang, DZ.,Ma, YW.,Huang, JF.,...&Chen, JG.(2015).Analysis of thorium and uranium based nuclear fuel options in Fluoride salt-cooled High-temperature Reactor.PROGRESS IN NUCLEAR ENERGY,78,285—290. |
| MLA | Li, XX,et al."Analysis of thorium and uranium based nuclear fuel options in Fluoride salt-cooled High-temperature Reactor".PROGRESS IN NUCLEAR ENERGY 78(2015):285—290. |
入库方式： OAI收割
来源：上海应用物理研究所
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