Definition of model-based control strategies for the Molten Salt Fast Reactor nuclear power plant-Reference-Cited by-同舟云学术

Definition of model-based control strategies for the Molten Salt Fast Reactor nuclear power plant

Published:2021-03 Issue: Volume:373 Page:111015
ISSN:0029-5493
Container-title:Nuclear Engineering and Design
language:en
Short-container-title:Nuclear Engineering and Design

Author:

Tripodo Claudio,Lorenzi Stefano,Cammi Antonio

Publisher

Elsevier BV

Subject

Mechanical Engineering,Waste Management and Disposal,Safety, Risk, Reliability and Quality,General Materials Science,Nuclear Energy and Engineering,Nuclear and High Energy Physics

Reference27 articles.

1. The Modelica Association, Modelica 3.2.2 Language Specification, 2014.

2. Calculating the effective delayed neutron fraction in the Molten Salt Fast Reactor: analytical, deterministic and Monte Carlo approaches;Aufiero;Ann. Nucl. Energy,2013

3. Bernard, J., 1999, Light water reactor control systems. Wiley Encyclopedia of Electrical and Electronics Engineering, New York, NY, USA: J. G. Webster, 1999.

4. On a new measure of interaction for multivariable process control;Bristol;IEEE Trans. Automat. Contr.,1966

5. Object-oriented modelling, simulation and control of IRIS nuclear power plant with modelica;Cammi,2005

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