Transition toward thorium fuel cycle in a molten salt reactor by using plutonium

doi:10.1007/s41365-017-0303-y

CORC > 上海应用物理研究所 > 中国科学院上海应用物理研究所 > 中科院上海应用物理研究所2011-2017年

	Transition toward thorium fuel cycle in a molten salt reactor by using plutonium
	Cui, DY; Xia, SP; Li, XX; Cai, XZ; Chen, JG
刊名	NUCLEAR SCIENCE AND TECHNIQUES
	2017
卷号	28 期号:10 页码:-
关键词	Msr Advantages
ISSN号	1001-8042
DOI	10.1007/s41365-017-0303-y
文献子类	期刊论文
英文摘要	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.
WOS关键词	MSR ; ADVANTAGES
语种	英语
WOS记录号	WOS:000411149700015
内容类型	期刊论文
源URL	[http://ir.sinap.ac.cn/handle/331007/28881]
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	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):-.