Cybersecurity Assessment Framework for Digital Interface Between Safety and Security at Nuclear Power Plants

Abstract This study aims to assess the cybersecurity aspects of nuclear power plants (NPPs) in regards to a digital safety-security interface. In traditional and advanced NPPs, safety and security functions are performed by analogue and digital systems. The risk of unauthorized software changing real-world system behaviors is a major and critical infrastructure safety and security issue. Within this context, a NPP is one of the most emblematic examples of critical infrastructure cyber targets. In this study, an evaluation of the functional impact of a cyber-attack targeting specific digital equipment in a nuclear facility is performed by means of a nuclear power plant simulator specifically developed for cybersecurity assessments, deployment of realistic cyber-attack simulation scenarios, and collection and evaluation of simulated data. The Asherah nuclear power plant simulator reproduces the dynamic behavior of a two-loop 2,772 MWt pressurized water reactor (PWR) including primary, secondary, and tertiary loops, as well as selected network infrastructure elements, communication protocols, and control systems. The system is projected to survive cyber-attacks, to allow great flexibility for digital systems and network research, and to allow the capture of data for an a posteriori analysis. The preliminary simulation results obtained by the deployment of realistic cyber-attack scenarios facilitated an understanding of the impacts of cyber-attacks, how they propagate in nuclear digital cyber-physical systems and their consequences, both in terms of plant security and safety.

[1]  T. Sathiyasheela Power series solution method for solving point kinetics equations with lumped model temperature and feedback , 2009 .

[2]  Yoshiaki Oka,et al.  Nuclear reactor Kinetics and Plant Control , 2013 .

[3]  Robert O. Lewis,et al.  Independent verification and validation , 1992 .

[4]  Chengcheng Deng,et al.  Best Estimate Plus Uncertainty analysis of a large break LOCA on Generation III reactor with RELAP5 , 2019, Annals of Nuclear Energy.

[5]  Barbaro Quintero-Leyva CORE: A numerical algorithm to solve the point kinetics equations , 2008 .

[6]  H. Kretzschmar,et al.  The IAPWS Industrial Formulation 1997 for the Thermodynamic Properties of Water and Steam , 2000 .

[7]  J.R.C. Piqueira,et al.  Advanced method for neutronics and system code coupling RELAP, PARCS, and MATLAB for instrumentation and control assessment , 2020 .

[8]  Kim Zetter,et al.  Countdown to Zero Day: Stuxnet and the Launch of the World's First Digital Weapon , 2014 .

[9]  R. B. Whitner,et al.  Guidelines for selecting and using simulation model verification techniques , 1989, WSC '89.

[10]  Mirela Gavrilas Safety Features of Operating Light Water Reactors of Western Design , 1994 .

[11]  Yu Huang,et al.  Mechanism model and simulation of pressurizer in the pressurized water reactor nuclear power plant , 2011, Proceedings of the 30th Chinese Control Conference.

[12]  J. Duderstadt,et al.  Nuclear reactor analysis , 1976 .

[13]  Juergen Schmidt Totally Integrated Automation , 2000 .

[14]  P. Yu. Belokrylov,et al.  Integration of the Computational Validation Process for Reactor Equipment into a Single Information Space to Create Digital Doppelgangers of Nuclear Energy Facilities , 2020 .

[15]  Robert G. Sargent,et al.  Verification and validation of simulation models , 2013, Proceedings of Winter Simulation Conference.

[16]  J. J. Cruz,et al.  Reactivity estimation during a reactivity-initiated accident using the extended Kalman filter , 2015 .

[17]  Kazimierz Duzinkiewicz,et al.  Nodal models of Pressurized Water Reactor core for control purposes – A comparison study , 2017 .

[19]  Charles Kim,et al.  A COURSE DEVELOPMENT PROJECT FOR HARDWARE DIVERSITY AND SOFTWARE RELIABILITY EDUCATION FOR DIGITAL INSTRUMENTATION AND CONTROL OF NUCLEAR POWER PLANT , 2011 .

[20]  J. Pechoušek,et al.  Virtual instrumentation technique used in the nuclear digital signal processing system design: Energy and time measurement tests , 2011 .

[21]  A. Aboanber Analytical solution of the point kinetics equations by exponential mode analysis , 2003 .

[22]  M. Kinard,et al.  Efficient numerical solution of the point kinetics equations in nuclear reactor dynamics , 2004 .

[23]  Dongbo Liu,et al.  Study on Cyber Security Risk Assessment of Digital Instrumentation &Control System of Nuclear Power Plant , 2018, 2018 International Conference on Power System Technology (POWERCON).