Use of advanced computational methods for reactivity estimation and instrumentation and control cyber security assessment in nuclear energy systems

• Grant number: 16/04600-0
• Support Opportunities: Regular Research Grants
• Start date: July 01, 2016
• End date: June 30, 2018
• Field of knowledge: Engineering - Electrical Engineering
• Principal Investigator: José Roberto Castilho Piqueira
• Grantee: José Roberto Castilho Piqueira
• Host Institution: Escola Politécnica (EP). Universidade de São Paulo (USP). São Paulo , SP, Brazil
• Associated researchers: Diego Alves Correa ; Felipe Ramos Antunes ; José Jaime da Cruz ; José Osvaldo de Souza Guimarães ; Luiz Felipe Peterle do Nascimento ; Ricardo Paulino Marques ; Rodney Aparecido Busquim e Silva

Abstract

The use of the KF predictive tool, an optimum estimator for linear systems, and derived filters, such as the EKF, in the nuclear field is not common. This work will implement a reactivity-forecasting toll, using a stochastic approach, to estimate a core-position dependent reactivity at HZP and HFP, assuming different neutron flux detectors core-positions, to mitigate or minimize the uncertainty and errors during the reactivity measurement. Moreover, the use of estimation tools in digital I&C cyber security is also not common. This work aims to implement an application of a dynamic system and state estimation to provide a point defense option against cyber attacks. Besides simulation activities, a hardware-in-the-loop (HIL) test bed, using field programmable gate array (FPGA) and programmable logic controllers (PLCs), will be implemented for testing purposes. The HIL will provide an opportunity to simulate the NPP conditions using the dynamic model, and by adding the hardware needed for the controlling task. The EKF, with adequate degree of accuracy, will allow the supervision of selected state variables, which may be object of a cyber attack. presents the I&C cyber security defense strategy. A traditional NPP will be modeled using the RELAP 5 or/and PARCS 3D codes. The IPK and the EKF modeling will be based on the point kinetics reactor equations (PKRE), using a state-space model, and they will be implemented using the MATLAB simulation environment. A set of real data will also be used as input for both algorithms. A benchmark strategy, using the codes and data, will be implemented. (AU)

Scientific publications

(References retrieved automatically from Web of Science and SciELO through information on FAPESP grants and their corresponding numbers as mentioned in the publications by the authors)

SILVA, R. A. BUSQUIM E; PIQUEIRA, J. R. C.; CRUZ, J. J.; MARQUES, R. P.. Cybersecurity Assessment Framework for Digital Interface Between Safety and Security at Nuclear Power Plants. INTERNATIONAL JOURNAL OF CRITICAL INFRASTRUCTURE PROTECTION, v. 34, SEP 2021. (16/04600-0)