H., M., & 57136356100. (2023). Neutronic assessment of triso particle fuels in a small fluoride salt-cooled high-temperature reactor. American Nuclear Society.
Chicago Style CitationH., Mohamed, and 57136356100. Neutronic Assessment of Triso Particle Fuels in a Small Fluoride Salt-cooled High-temperature Reactor. American Nuclear Society, 2023.
MLA引文H., Mohamed, and 57136356100. Neutronic Assessment of Triso Particle Fuels in a Small Fluoride Salt-cooled High-temperature Reactor. American Nuclear Society, 2023.
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