Journal of Nuclear Science, Engineering and Technology (JONSAT)
In cooperation with the Iranian Nuclear Society

Computational Transient Model of a Pressurizer in Light Water PWR

Document Type : Research Paper

Authors

M Moubed
A Hossini Ghafar
Abstract
The pressurizer component controls and maintains the pressure within the primary loop in Pressurized Water Reactor (PWR). It plays a vital role in the safe operation of PWRs. In this paper, the dynamic behavior of a pressurizer in transient condition is simulated. A numerical model based on three control volumes is considered to simulate the behavior of the pressurizer in transient condition. These three areas include the vapor region, saturated water in contact with vapor region and the region where the surged water is mixed with the water within the pressurizer. In the developed model, wall condensation, spray condensation, evaporation, bulk boiling and the energy absorption through the heater and heat transfer through the wall to ambient phenomena are taken into account. The mass, energy conservation with water-steam state equations are used to calculate the pressurizer pressure, water level and temperatures of each region. The presented model is developed as a software package so as the user can simulate all the available transient with a great ease. Specifically, by using the developed software, heater on/off, spray, in-surge, out-surge and opening of relief valve can be simulated by the user action or through predefined scenarios. The Massachusetts Institute of Technology (MIT) pressurizer test facility experimental data for in-surge, out-surge and out-surge after in-surge transients, are used to validate the developed model.

Highlights

  1. G. Leoni, G. Santarossa, Critical Comparison between Theoretical and Experimental Transients of the Enrico Fermi PWR, Energia Nucleare, 14 (1967).

 2.   A.N. Nahavandi, S. Mackenchery, An Improved Pressurizer Model with Bubble Rise and Condensate Drop Dynamics, Nuclear Engr. and Des. 12 (1970) 135.

 3.   R.C. Baron, Digital Model Simulation of a Nuclear Pressurizer, Nuclear Sci. and Engr. S2 (1973) 283.

 4.   E. Takasuo, Modeling of Pressurizer Using APROS and TRACE Thermal Hydraulic Codes, (2006).

 5.   APROS (Advanced Process Simulation Environment) (Vihavainen et al.,1999) has been developed in Finland.

 6.   TRACE (TRAC/RELAP Advanced Computational Engine) (USNRC, 2005) is the thermal hydraulic tools developed at the USNRC.

 7.   S. Kim, An Experimental and Analytical Model of a PWR Pressurizer during Transients, Massachusetts Institute of Technology, Ph. D Thesis (1984).

 8.   U.S. Department of Energy Washington, D.C. 20585, DOE FUNDAMENTALS HAND-BOOK MECHANICAL SCIENCE, 2 of 2 (1993).

 9.   Y.A. Çengel Heat and Mass Transfer: A Practical Approach, (2007).

 10.http://www.x-eng.com.

Keywords

Simulation
Pressurizer
Transient Behavior
PWR
  1. G. Leoni, G. Santarossa, Critical Comparison between Theoretical and Experimental Transients of the Enrico Fermi PWR, Energia Nucleare, 14 (1967).

 2.   A.N. Nahavandi, S. Mackenchery, An Improved Pressurizer Model with Bubble Rise and Condensate Drop Dynamics, Nuclear Engr. and Des. 12 (1970) 135.

 3.   R.C. Baron, Digital Model Simulation of a Nuclear Pressurizer, Nuclear Sci. and Engr. S2 (1973) 283.

 4.   E. Takasuo, Modeling of Pressurizer Using APROS and TRACE Thermal Hydraulic Codes, (2006).

 5.   APROS (Advanced Process Simulation Environment) (Vihavainen et al.,1999) has been developed in Finland.

 6.   TRACE (TRAC/RELAP Advanced Computational Engine) (USNRC, 2005) is the thermal hydraulic tools developed at the USNRC.

 7.   S. Kim, An Experimental and Analytical Model of a PWR Pressurizer during Transients, Massachusetts Institute of Technology, Ph. D Thesis (1984).

 8.   U.S. Department of Energy Washington, D.C. 20585, DOE FUNDAMENTALS HAND-BOOK MECHANICAL SCIENCE, 2 of 2 (1993).

 9.   Y.A. Çengel Heat and Mass Transfer: A Practical Approach, (2007).

 10.http://www.x-eng.com.

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