Burnup optimization of once-through molten salt reactors using enriched uranium and thorium-Reference-Cited by-同舟云学术

Burnup optimization of once-through molten salt reactors using enriched uranium and thorium

Published:2022-01 Issue:1 Volume:33 Page:
ISSN:1001-8042
Container-title:Nuclear Science and Techniques
language:en
Short-container-title:NUCL SCI TECH

Author:

Tan Meng-Lu^ORCID,Zhu Gui-Feng^ORCID,Zhang Zheng-De,Zou Yang^ORCID,Yu Xiao-Han,Yu Cheng-Gang^ORCID,Dai Ye,Yan Rui^ORCID

Publisher

Springer Science and Business Media LLC

Subject

Nuclear Energy and Engineering,Nuclear and High Energy Physics

Link

https://link.springer.com/content/pdf/10.1007/s41365-022-00995-2.pdf

Reference35 articles.

1. J. Krepel, B. Hombourger, V. Bykov et al., Molten salt reactor with simplified fuel recycling and delayed carrier salt cleaning, in Paper Presented at the 22th International Conference on Nuclear Engineering ICONE'22 (Prague, 2014)

2. J.H. Wu, C.G. Yu, C.Y. Zou et al., Core design optimization for a novel heavy water moderated molten salt reactor. Nucl. Tech. 44(8), 080601 (2021). https://doi.org/10.11889/j.0253-3219.2021.hjs.44.080601 (in Chinese)

3. C.Y. Zou, J.H. Wu, C.G. Yu et al., Influence of reprocessing efficiency on fuel cycle performances for molten salt reactor. Nucl. Tech. 44(10), 100602 (2021). https://doi.org/10.11889/j.0253-3219.2021.hjs.44.100602 (in Chinese)

4. J. Serp, M. Allibert, O. Benes et al., The molten salt reactor (MSR) in generation IV: overview and perspectives. Prog. Nucl. Energy 77, 308–319 (2014). https://doi.org/10.1016/j.pnucene.2014.02.014

5. M.S. Kazimi, E.J. Moniz, C. Forsberg, The Future of the Nuclear Fuel Cycle, 1st edn. (Massachusetts Institute of Technology, The United States, 2011), pp. 20–22

Cited by 11 articles. 订阅此论文施引文献订阅此论文施引文献，注册后可以免费订阅5篇论文的施引文献，订阅后可以查看论文全部施引文献

1. Assessing the benefit of thorium fuel in a once through molten salt reactor;Progress in Nuclear Energy;2024-11

2. Investigating geometry adjustments for enhanced performance in a PeLUIt-10 MWt pebble bed HTGR with OTTO refueling scheme;Nuclear Engineering and Design;2024-06

3. Core Optimization for Extending the Graphite Irradiation Lifespan in a Small Modular Thorium-Based Molten Salt Reactor;Journal of Nuclear Engineering;2024-05-10

4. Experimental and numerical investigation into a thermocline storage for district heating;Applied Thermal Engineering;2024-05

5. On the Employment of a Chloride or Floride Salt Fuel System in Advanced Molten Salt Reactors, Part 2; Core Inventory, Fuel Burnup, and Salt Clean-Up System;Energies;2024-03-19