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Cited article:

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Assessment of Reactor Physics Characteristics of Prismatic Fuel Concepts With a Hydrogen-Based Moderator for Use in a Fluoride Salt-Cooled Small Modular Reactor

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Journal of Nuclear Engineering and Radiation Science 10 (2) (2024)
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Evaluation of thermal neutron scattering law of nuclear-grade isotropic graphite

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Preliminary safety analysis for a heavy water-moderated molten salt reactor

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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