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Cited article:

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

Omid Noori-kalkhoran, Lakshay Jain, Lewis Powell, Andrew Jones, Daliya Aflyatunova and Bruno Merk
Energies 17 (6) 1475 (2024)
https://doi.org/10.3390/en17061475

A review of nuclear electric fission space reactor technologies for achieving high-power output and operating with HALEU fuel

Aiden Peakman and Ben Lindley
Progress in Nuclear Energy 163 104815 (2023)
https://doi.org/10.1016/j.pnucene.2023.104815

Comparative Study on the Neutronic Performance of Thermal and Fast Molten Salt Reactors under Once-Through Fuel Cycle

Changqing Yu, Guifeng Zhu, Yafen Liu, et al.
International Journal of Energy Research 2023 1 (2023)
https://doi.org/10.1155/2023/8875215

Neutronic and fuel cycle performance analysis of fluoride and chloride fuels in Molten Salt Fast Reactor (MSFR)

M. Aghili Nasr, A. Zolfaghari, R. Akbari, A. Cammi and S. Amirkhosravi
Nuclear Engineering and Design 413 112506 (2023)
https://doi.org/10.1016/j.nucengdes.2023.112506

Assembly-level analysis on temperature coefficient of reactivity in a graphite-moderated fuel salt reactor fueled with low-enriched uranium

Xiao-Xiao Li, De-Yang Cui, Chun-Yan Zou, Jian-Hui Wu, Xiang-Zhou Cai and Jin-Gen Chen
Nuclear Science and Techniques 34 (5) (2023)
https://doi.org/10.1007/s41365-023-01216-0

Electroanalytical Measurements of UCl3 and CeCl3 in Molten NaCl-CaCl2

Huan Zhang, Suhee Choi, D. Ethan Hamilton and Michael F. Simpson
Journal of The Electrochemical Society 168 (5) 056521 (2021)
https://doi.org/10.1149/1945-7111/ac0222

SIMULATION OF BREED AND BURN FUEL CYCLE OPERATION OF MOLTEN SALT REACTOR IN BATCH-WISE REFUELING MODE

Valeria Raffuzzi, Jiri Krepel, M. Margulis and P. Blaise
EPJ Web of Conferences 247 13003 (2021)
https://doi.org/10.1051/epjconf/202124713003