Background
Type: Article

Stability analysis and parametric study of natural circulation integrated self-pressurized water reactor

Journal: Annals of Nuclear Energy (03064549)Year: May 2020Volume: 139Issue:
Pilehvar A.F. Esteki M.H.Ansarifar G.a Hedayat A.
DOI:10.1016/j.anucene.2019.107279Language: English

Abstract

The stability analysis of a natural circulation integrated self-pressurized water reactor is investigated by the Lyapunov approach. The analysis of the pressurized water reactors (PWRs), particularly the integrated self-pressurized water reactors, is essential in keeping the neutronic and thermal-hydraulic parameters of the system stable. An appropriate nonlinear dynamic model is introduced based on conservation of mass, momentum and energy which is then linearized, in a state-space model. The Lyapunov approach and Routh-Hurwitz criterion are applied to assess the stability of this linearized system over its entire power range. The analysis is done for the primary coolant circuit in the RPV by assuming the steam dome pressure as the fixed parameter. It is found that the system remains stable over its entire power range. The influence of different geometrical features is studied at nominal conditions. It has been found that by reducing the chimney height results in a decrease in the coolant flow rate and a downward motion of the onset of flashing while the average core coolant temperature rises. For lower values of friction losses coefficient, the coolant flow rate increases, and the onset of flashing moves upward and the average core coolant temperature decreases. A change in independent parameters, which are effective in generating the natural circulation of the coolant, can influence the inherent safety of the system: An increase in reactor power and chimney height and a decrease in friction losses coefficient improve the system inherent safety. Two input functions as extra reactivity for increasing and decreasing the power from the nominal state are implemented into the dynamic model and the model response is therefore assessed by considering the lack of two phase flow entry to the core restriction. The boundary of the system stability lies in the range 32–107 MWt and using the system outside this range the system pressure needs to be controlled through spray and heater systems. The obtained results are based on the initial information, data and primary design of these types of reactors. Determining a more accurate boundary requires more detailed design and assessment together with experimental test facilities with respect to other restricting parameters of the system. The results presented in this paper can be implemented in further research on this type of reactors, particularly for nonlinear stability analysis and finding nonlinear Lyapunov function. © 2019 Elsevier Ltd


Author Keywords

Dynamic modeliPWRLyapunov approachRouth-Hurwitz criterionSMRStability analysisState-space model

Other Keywords

ChimneysCoolantsDynamic modelsFrictionLinearizationLyapunov functionsNatural convectionNonlinear analysisSmall nuclear reactorsState space methodsSystem stabilityTwo phase flowiPWRLyapunov approachRouth-Hurwitz criterionStability analysisState - space modelsPressurized water reactors