Numerical analysis of transient pressure variation in the condenser of a nuclear power station

• Published in: Journal of mechanical science and technology 2016, 30(2), , pp.953-962
• Main Authors: Wang, Xinjun, Zhou, Zijie, Song, Zhao, Lu, Qiankui, Li, Jiafu
• Format: Article
• Language: English
• Subjects: Coefficient of variation; Computer simulation; Constants; Control; Cooling; Cooling rate; Dynamical Systems; Engineering; Flow velocity; Fluctuation; FORTRAN; Heat transfer coefficients; Industrial and Production Engineering; Initial conditions; Mathematical models; Mechanical Engineering; Nuclear energy; Nuclear power plants; Nuclear power stations; Numerical analysis; Vibration; Water flow; 기계공학
• ISSN: 1738-494X; 1976-3824
• DOI: 10.1007/s12206-016-0149-y

To research the characteristics of the transient variation of pressure in a nuclear power station condenser under accident condition, a mathematical model was established which simulated the cycling cooling water, heat transfer and pressure in the condenser. The calculation program of transient variation characteristics was established in Fortran language. The pump’s parameter, cooling line’s organization, check valve’s feature and the parameter of siphonic water-collecting well are involved in the cooling water flow’s mathematical model. The initial conditions of control volume are determined by the steady state of the condenser. The transient characteristics of a 1000 MW nuclear power station’s condenser and cooling water system were examined. The results show that at the condition of plant-powersuspension of pump, the cooling water flow rate decreases rapidly and refluxes, then fluctuates to 0. The variation of heat transfer coefficient in the condenser has three stages: at start it decreases sharply, then increases and decreases, and keeps constant in the end. Under three conditions (design, water and summer), the condenser pressure goes up in fluctuation. The time intervals between condenser’s pressure signals under three conditions are about 26.4 s, which can fulfill the requirement for safe operation of nuclear power station.