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All issues EPJ Nuclear Sci. Technol., 5 (2019) 15 Article references

Articles citing this article

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Cited article:

The minimum burnup requirement analysis for molten chlorine-salt fast reactor

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Nuclear Engineering and Design 432 113831 (2025)
https://doi.org/10.1016/j.nucengdes.2025.113831

Summary of researches on operational characteristics and safety of molten salt fast reactors based on neutronics and thermal-hydraulics coupling analysis

Hiroyasu Mochizuki
Nuclear Engineering and Design 435 113941 (2025)
https://doi.org/10.1016/j.nucengdes.2025.113941

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

Transient Covalency in Molten Uranium(III) Chloride

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Journal of the American Chemical Society 146 (31) 21220 (2024)
https://doi.org/10.1021/jacs.4c05765

Rapid and accurate determination of chlorine isotopic ratios with ICP-MS/MS using O2 reaction gas

Tyler D. Schlieder, Nicole D. Rocco, Maria Laura di Vacri, Isaac J. Arnquist, Danny Bottenus, Zachary Huber and Bruce McNamara
Journal of Analytical Atomic Spectrometry 39 (10) 2502 (2024)
https://doi.org/10.1039/D4JA00191E

Thermodynamic assessment of the LiF BaF2 ZrF4 system

Thomas Dumaire, Luuk Groot, Nynke M. Schakenraad, Ondrej Beneš, Rudy J.M. Konings and Anna L. Smith
Fluid Phase Equilibria 585 114147 (2024)
https://doi.org/10.1016/j.fluid.2024.114147

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

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

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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

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