Low enriched uranium and thorium fuel utilization under once-through and offline reprocessing scenarios in small modular molten salt reactor
文献类型：期刊论文
| 作者 | Zhu, GF; Zou, Y; Yan, R; Tan, ML; Zou, CY; Kang, XZ; Chen, JG; Guo, W; Dai, Y |
| 刊名 | INTERNATIONAL JOURNAL OF ENERGY RESEARCH
 |
| 出版日期 | 2019 |
| 卷号 | 43期号:11页码:5775-5787 |
| 关键词 | DESIGN |
| ISSN号 | 0363-907X |
| DOI | 10.1002/er.4676 |
| 文献子类 | 期刊论文 |
| 英文摘要 | Using low enrichment uranium as driver fuel under once-through mode in molten salt reactor (MSR) attracts more and more attention because of its fuel availability, no new technology, and nuclear nonproliferation. It is regarded as a wise research and development road to shorten deployment time of MSRs and to prepare techniques and experiences for thorium-uranium breeding of MSRs in the future. However, this fuel management is still faced with some different technical routes, such as the selection of carrier salts, the enrichment of uranium, with or without thorium, and the recycle necessary of spent nuclear fuel. Therefore, various fuel cycle schemes were compared and analyzed using an in-house developed fuel management code MOBAT. Different graphite assemblies were optimized by changing the salt volume fraction in core and dimension to find a region for best fuel utilization and negative temperature reactivity coefficient. Prismatic block with 10% volume fraction of molten salt is considered as a good assembly type because of its significant space shielding effect of U-238. For carrier salts, LiF-BeF2 with 99.995% enriched Li-7 displays higher fuel utilization and lower cost of fuel cycle than NaF-BeF2, while the tritium production at the beginning of life will be two orders of magnitude higher. For fuel enrichment, 20% enriched uranium is recommended because the background of neutron absorption from carrier salt and graphite will be more significant in lower enrichment condition. Importantly, it shows that thorium is a good breed and burned fuel in situ and could improve the fuel utilization by 20%. Also, offline reprocessing to recover the uranium is a commendable scheme when the cost of offline reprocessing is lower than 400 $/kgHN. |
| 语种 | 英语 |
| 源URL | [http://ir.sinap.ac.cn/handle/331007/32117]  |
| 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,Zou, Y,Yan, R,et al. Low enriched uranium and thorium fuel utilization under once-through and offline reprocessing scenarios in small modular molten salt reactor[J]. INTERNATIONAL JOURNAL OF ENERGY RESEARCH,2019,43(11):5775-5787. |
| APA | Zhu, GF.,Zou, Y.,Yan, R.,Tan, ML.,Zou, CY.,...&Dai, Y.(2019).Low enriched uranium and thorium fuel utilization under once-through and offline reprocessing scenarios in small modular molten salt reactor.INTERNATIONAL JOURNAL OF ENERGY RESEARCH,43(11),5775-5787. |
| MLA | Zhu, GF,et al."Low enriched uranium and thorium fuel utilization under once-through and offline reprocessing scenarios in small modular molten salt reactor".INTERNATIONAL JOURNAL OF ENERGY RESEARCH 43.11(2019):5775-5787. |
入库方式： OAI收割
来源：上海应用物理研究所
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