Zobrazeno 1 - 10
of 13
pro vyhledávání: '"Sun, Ducheng"'
Autor:
Sun, Ducheng, You, Ersheng, Zhang, Ting, Xu, Jianjun, Wang, Xiaokai, Ren, Xingjie, Tao, Wenquan
Publikováno v:
In International Communications in Heat and Mass Transfer December 2024 159 Part B
Publikováno v:
Progress in Nuclear Energy. 91:295-301
The fourth stage Automatic Depressurization System is an important passive safety feature in Westinghouse AP1000 which enables controlled depressurization of reactor coolant system in small break LOCA. However, large amount of coolant can be carried
Publikováno v:
Progress in Nuclear Energy. 80:80-85
Upper plenum liquid entrainment can reduce the coolant inventory in the reactor pressure vessel and poses great threats to core uncovering and melting in the accident conditions. To make up for the deficiency of upper plenum entrainment database, the
Publikováno v:
Annals of Nuclear Energy. 76:315-322
Tee branches are widely used in nuclear power plants for varying purposes. The tee branch is adopted by the fourth stage Automatic Depressurization System (ADS-4) in Westinghouse AP600/AP1000 to depressurize the primary loop during the small break lo
Publikováno v:
Experimental Thermal and Fluid Science. 57:317-323
ADS-4 branch line provides a controlled depressurization of the Westinghouse AP600/AP1000 primary loop during a small break LOCA. However, the coolant will be entrained to the containment simultaneously which leads to the loss of liquid inventory. AD
Publikováno v:
Progress in Nuclear Energy. 74:71-78
ADS-4 is an important passive safety feature in AP1000 design which provides a controlled depressurization. In this paper, reduced diameter and height scaling analysis with identical fluid properties was conducted on AP1000 ADS-4 blowdown and depress
Publikováno v:
Volume 2A: Thermal Hydraulics.
In order to gain more insights into the system depressurization and entrainment behavior after actuation of the fourth-stage (ADS-4) valves during a loss-of-coolant-accident, the ADS-4 Depressurization and Entrainment TEst Loop (ADETEL) scaled to AP1
Publikováno v:
Volume 2A: Thermal Hydraulics.
The thermal-hydraulic characteristics of Nuclear Power Plant (NPP) during Steam Generator Tube Rupture (SGTR) accident are of great concern. In this paper, the thermal-hydraulic characteristics of CP300 during SGTR accident with no operator actionsdu
Complexes of Acetone Ferrocenecarbonylhydrazone with Hydrated Lanthanide Chlorides and Thiocyanates.
Publikováno v:
Synthesis & Reactivity in Inorganic & Metal-Organic Chemistry; Aug1992, Vol. 22 Issue 8, p1169-1182, 14p