TAILIEUCHUNG - Development of a control-oriented power plant simulator for the molten salt fast reactor

In this paper, modelling and simulation of a control-oriented plant-dynamics tool for the molten salt fast reactor (MSFR) is presented. The objective was to develop a simulation tool aimed at investigating the plant response to standard control transients, in order to support the system design finalization and the definition of control strategies. | Development of a control-oriented power plant simulator for the molten salt fast reactor EPJ Nuclear Sci. Technol. 5 13 2019 Nuclear Sciences C. Tripodo et al. published by EDP Sciences 2019 amp Technologies https epjn 2019029 Available online at https REGULAR ARTICLE Development of a control-oriented power plant simulator for the molten salt fast reactor Claudio Tripodo Andrea Di Ronco Stefano Lorenzi and Antonio Cammi Politecnico di Milano Department of Energy Nuclear Engineering Division Via La Masa 34 20156 Milan Italy Received 9 April 2019 Received in final form 27 July 2019 Accepted 26 August 2019 Abstract. In this paper modelling and simulation of a control-oriented plant-dynamics tool for the molten salt fast reactor MSFR is presented. The objective was to develop a simulation tool aimed at investigating the plant response to standard control transients in order to support the system design finalization and the definition of control strategies. The simulator was developed employing the well tested flexible and open-source object- oriented Modelica language. A one-dimensional modelling approach was used for thermal-hydraulics and heat transfer. Standard and validated thermal-hydraulic Modelica libraries were employed for various plant components tubes pumps turbines etc. . An effort was spent in developing a new MSR library modelling the 1D flow of a liquid nuclear fuel including an ad-hoc neutron-kinetics model which properly takes into consideration the motion of the Delayed Neutron Precursors along the fuel circuit and the consequent reactivity insertion due to the variation of the effective delayed fractions. An analytical steady-state 2-D model of the core and the fuel circuit was developed using MATLAB in order to validate the Decay Neutron Precursors model implemented in the plant simulator. The plant simulator was then employed to investigate the plant dynamics in response to three transients variation of fuel flow rate .

• Năng lượng
• Control oriented plant dynamics tool
• Molten salt fast reactor
• Standard control transient
• Control oriented power plant simulator
• Analytical steady state 2 D model