A novel concept for a molten salt reactor moderated by heavy water

doi:10.1016/j.anucene.2019.04.043

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

	A novel concept for a molten salt reactor moderated by heavy water
	Wu, JH ; Chen, JG ; Kang, XZ ; Li, XX ; Yu, CG ; Zou, CY ; Cai, XZ
刊名	ANNALS OF NUCLEAR ENERGY
	2019
卷号	132 页码:391-403
关键词	FUEL-CYCLE BREEDING RATIO CORE DESIGN GRAPHITE
ISSN号	0306-4549
DOI	10.1016/j.anucene.2019.04.043
文献子类	期刊论文
英文摘要	The Heavy Water moderated Molten Salt Reactor (HW-MSR) is a novel concept of a thermal heterogeneous nuclear reactor and pursues for Thorium-Uranium (Th-U) breeding. It adopts heavy water rather than graphite as moderator while employs the same liquid fuel of molten salt reactor (MSR). Thus this new concept inherits the positive properties of MSR (feasible for online reprocessing) and heavy water reactor (high neutron moderating ratio). Furthermore it can address the problems of depleted graphite management and positive temperature coefficient due to neutron spectral shift propitious to U-233 fission existed in Molten Salt Breeding Reactor (MSBR). HW-MSR consists of the primary loop system, intermediate cooling loop, energy conversion system, external cooling system and online reprocessing system. Since there is a huge temperature difference between molten salt (higher than 600 degrees C) and heavy water (lower than 100 degrees C to keep high density) in the core, effectively preventing the heat transfer between them is one main challenge. To address this problem, a thermal insulator made of Yttria Stabilized Zirconia (YSZ) is applied and analyzed. The calculation results show that both the fuel salt and moderator outlet temperature across the core can satisfy the design requirements. Similar to a traditional MSR, the HW-MSR also implements an online reprocessing system which can online extract and recycle useful fuel during operation, providing a feasible approach for Th-U fuel cycle. In addition, because of the outstanding neutron performance of heavy water moderator, a small initial U-233 loading mass is required for HW-MSR, and its breeding ratio can achieve 1.073, corresponding to a doubling time of 12 years at the reprocessing cycle of 10 days. Compared with traditional light water reactor (LWR) whose transuranium (TRU) production is 69 kg/GWy, HW-MSR produces only 0.51 kg/GWy. This much lower radiotoxicity of nuclear waste in the HW-MSR would significantly enhance the sustainability of nuclear energy. (C) 2019 Elsevier Ltd. All rights reserved.
语种	英语
内容类型	期刊论文
源URL	[http://ir.sinap.ac.cn/handle/331007/31949]
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	1.Chinese Acad Sci, CAS Innovat Acad TMSR Energy Syst, Shanghai 201800, Peoples R China; 2.Univ Chinese Acad Sci, Beijing 100049, Peoples R China 3.Chinese Acad Sci, Shanghai Inst Appl Phys, Shanghai 201800, Peoples R China;
推荐引用方式 GB/T 7714	Wu, JH,Chen, JG,Kang, XZ,et al. A novel concept for a molten salt reactor moderated by heavy water[J]. ANNALS OF NUCLEAR ENERGY,2019,132:391-403.
APA	Wu, JH.,Chen, JG.,Kang, XZ.,Li, XX.,Yu, CG.,...&Cai, XZ.(2019).A novel concept for a molten salt reactor moderated by heavy water.ANNALS OF NUCLEAR ENERGY,132,391-403.
MLA	Wu, JH,et al."A novel concept for a molten salt reactor moderated by heavy water".ANNALS OF NUCLEAR ENERGY 132(2019):391-403.