Zobrazeno 1 - 10
of 10
pro vyhledávání: '"Longkun He"'
Autor:
Yatai Li, Longkun He, Di Xie, Anqi Zhao, Lixin Wang, Nathan M. Kreisberg, John Jayne, Yingjun Liu
Publikováno v:
Environment International, Vol 165, Iss , Pp 107305- (2022)
Many manmade organic air pollutants are semivolatile and primarily used and exposed indoors. It remains unclear how indoor environmental parameters affect indoor air dynamics of semivolatile organic compounds (SVOCs) in real-world indoor conditions,
Externí odkaz:
https://doaj.org/article/bf62d43ad997432f91e57f73516e0ce2
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2019 (2019)
Reactor pressure vessel (RPV) support is a key safety facility which is categorized as Class 1 in the ASME nuclear safety design. The temperature distribution of RPV support is one of the key considerations for the concrete safety contacting with the
Externí odkaz:
https://doaj.org/article/866c04bdb2e145c19ebea5a6ce362f40
Suppressed atmospheric chemical aging of cooking organic aerosol particles in wintertime conditions.
Publikováno v:
Atmospheric Chemistry & Physics Discussions; 11/27/2023, p1-17, 17p
Publikováno v:
Atmospheric Measurement Techniques Discussions; 8/31/2023, p1-22, 22p
Publikováno v:
Nuclear Science and Engineering. 195:367-390
Jet fragmentation greatly influences the possibility of steam explosion and the formation of a debris bed when a molten corium jet falls into subcooled coolant during a severe accident of a nuclear...
Autor:
Yatai Li, Di Xie, Longkun He, Anqi Zhao, Lixin Wang, Nathan M. Kreisberg, John Jayne, Yingjun Liu
Publikováno v:
Building and Environment. 223:109446
Publikováno v:
Science and Technology of Nuclear Installations, Vol 2019 (2019)
Reactor pressure vessel (RPV) support is a key safety facility which is categorized as Class 1 in the ASME nuclear safety design. The temperature distribution of RPV support is one of the key considerations for the concrete safety contacting with the
Publikováno v:
Annals of Nuclear Energy. 143:107392
In nuclear power plants, core melt accidents are often accompanied with fuel–coolant interactions (FCI), which may escalate to steam explosion destroying the integrity of structural components and even the containment under certain conditions. The
Publikováno v:
Volume 6B: Thermal-Hydraulics and Safety Analyses.
In vessel retention (IVR) of molten core debris via water cooling at the external surface of the reactor vessel is an important severe accident management feature of advanced passive plants. During postulated severe accidents, the heat generated due
Publikováno v:
Volume 6B: Thermal-Hydraulics and Safety Analyses.
In nuclear power plants, fuel-coolant interaction (FCI) often accompanied with core melt accidents, which may escalate to steam explosion destroying the integrity of structural components and even the containment under certain conditions. In the pres