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Thorium utilization with pebble mixing system in fluoride salt-cooled High Temperature Reactor
Zhu, GF; Liu, SJ; Zou, Y; Yan, R; Tan, ML; Kang, XZ; Li, MH; Zhou, B; Dai, Y
2019
Source PublicationPROGRESS IN NUCLEAR ENERGY
ISSN0149-1970
Volume114Issue:-Pages:84—90
Subtype期刊论文
AbstractMixing 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.
KeywordURANIA FUEL CORE
DOI10.1016/j.pnucene.2019.02.005
Indexed BySCI
Language英语
Citation statistics
Document Type期刊论文
Identifierhttp://ir.sinap.ac.cn/handle/331007/31878
Collection中科院上海应用物理研究所2011-2020年
AffiliationChinese Acad Sci, Shanghai Inst Appl Phys, Shanghai 201800, Peoples R China
Recommended Citation
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.
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