Guo, Z., & Xiao, S. (2025). Thermal hydraulic study of NuScale iPWR passive containment cooling behaviour during loss-of-coolant accident. International Journal of Advanced Nuclear Reactor Design and Technology, 7(2), 100. https://doi.org/10.1016/j.jandt.2025.05.003
Chicago-referens (17:e uppl.)Guo, Zhexi, och Sicong Xiao. "Thermal Hydraulic Study of NuScale IPWR Passive Containment Cooling Behaviour During Loss-of-coolant Accident." International Journal of Advanced Nuclear Reactor Design and Technology 7, no. 2 (2025): 100. https://doi.org/10.1016/j.jandt.2025.05.003.
MLA-referens (9:e uppl.)Guo, Zhexi, och Sicong Xiao. "Thermal Hydraulic Study of NuScale IPWR Passive Containment Cooling Behaviour During Loss-of-coolant Accident." International Journal of Advanced Nuclear Reactor Design and Technology, vol. 7, no. 2, 2025, p. 100, https://doi.org/10.1016/j.jandt.2025.05.003.
