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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
2019
Source PublicationANNALS OF NUCLEAR ENERGY
ISSN0306-4549
Volume132Pages:391-403
Subtype期刊论文
AbstractThe 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.
KeywordFUEL-CYCLE BREEDING RATIO CORE DESIGN GRAPHITE
DOI10.1016/j.anucene.2019.04.043
Indexed BySCI
Language英语
Citation statistics
Document Type期刊论文
Identifierhttp://ir.sinap.ac.cn/handle/331007/31949
Collection中科院上海应用物理研究所2011-2020年
Affiliation1.Chinese Acad Sci, Shanghai Inst Appl Phys, Shanghai 201800, Peoples R China;
2.Chinese Acad Sci, CAS Innovat Acad TMSR Energy Syst, Shanghai 201800, Peoples R China;
3.Univ Chinese Acad Sci, Beijing 100049, Peoples R China
Recommended Citation
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.
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