Safety and security aspects in design of digital safety I&C in nuclear power plants
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Y. Ding
Abstract
The paper describes a safety objective oriented systematic design approach of digital (computerized) safety I&C in modern nuclear power plants which considers the plant safety requirements as well as cybersecurity needs. The defence in depth philosophy is applied by using different defence lines in the I&C architecture and protection zones in the plant IT environment.
Kurzfassung
Im Beitrag wird ein schutzzielorientierter systematischer Entwurfsprozess der digitalen (rechnerbasierten) Sicherheitsleittechnik in modernen Kernkraftwerken beschrieben. Dabei werden sowohl Aspekte der Sicherheitsanforderungen als auch Aspekte der Cybersecurity-Vorkehrungen berücksichtigt. Die gestaffelten Verteidigungslinien in der leittechnischen Architektur sowie Schutzzonen der IT-Landschaft spielen dabei eine zentrale Rolle.
References
1 AREVA GmbH: TELEPERM XS – The Digital I&C System for Functions Important to Safety in Nuclear Power Plants. Firmendruck, Areva NP GmbH, Erlangen/Germany, 2009Suche in Google Scholar
2 Ding, Y.: Automation of an entire nuclear power plant, taking Tianwan, China, as an Example. WANO-Workshop Computer based I&C-systems: necessity for continuous improvement, WANO Paris-Centre, 2001Suche in Google Scholar
3 Xu, X.; LiY.; Ding, Y.: Design Optimization and Operational Experiences of Digital Safety I&C. Tianwan NPP/China. Symposium Digital Safety I&C, S. 14–18, TÜV Nord Akademie, 2010Suche in Google Scholar
4 Broad, W. J.; Markoff, J.; Sanger, D. E: Israeli Test on Worm Called Crucial in Iran Nuclear Delay. The New Yorker Times, January 15, 2011Suche in Google Scholar
5 Graf, A.: From Safety Objectives to the I&C Design. IAEA workshop on Obsolescence Issues and Digital I&C Modernization Approaches in Buenos Aires, Argentina, March 2013Suche in Google Scholar
6 Ding, Y.: Schutzzielorientiertes Design der Sicherheitsleittechnik, atp edition, 56 (2014) 54–61, Vulkan Verlag201410.17560/atp.v56i05.2248Suche in Google Scholar
7 SEWD-Richtlinie: Richtlinie für den Schutz von IT-Systemen in kerntechnischen Anlagen und Einrichtungen der Sicherheitskategorien I und II gegen Störmaßnahmen oder sonstige Einwirkungen Dritter, VS NfD, German Federal Ministry for the Environment, Nature Conservation, Building and Nuclear Safety (BMUB), 2013Suche in Google Scholar
8 IT-Sicherheitsgesetz: Gesetz zur Erhöhung der Sicherheit informationstechnischer Systeme, German law for IT-Security, 25th July 2015Suche in Google Scholar
9 IEC 62443-x-x: Industrial communication networks – Network and system security – different parts, 2013Suche in Google Scholar
10 IEC 62859: Nuclear Power Plants – I&C Systems – Requirements for Coordinating Safety and Cybersecurity (Draft), 2015Suche in Google Scholar
11 IAEA NSS 17: Nuclear Security Series No. 17, Technical Guidance, Computer Security at Nuclear Facilities, 2011Suche in Google Scholar
12 Waedt, K.: Establishing Cyber Security Programs for I&C Systems at Nuclear Facilities, 2012, 43rd Annual Meeting on Nuclear Technology, Stuttgart, GermanySuche in Google Scholar
13 Waedt, K.; Ding, Y.; Gao, Y.; XieX.: I&C Modeling for Cybersecurity Analyses. 1st TÜV Rheinland China Symposium – Functional Safety in Nuclear and Industrial Applications, Shanghai, October 2015Suche in Google Scholar
14 Waedt, K.; Parekh, M.; Tong, X.; Gao, Y.; Ding, Y.; Xie, X.: Nuclear Safety and Risk-based Cybersecurity Testing. paper accepted for 47rd Annual Meeting on Nuclear Technology, Hamburg, Germany, May 2016Suche in Google Scholar
15 Fischer, R.; Clausing, R.; Dittmann, J.; KiltzS.; DingY.: Modeling Attacks on Critical Infrastructure: A first Summary of existing Approaches. paper accepted for 47rd Annual Meeting on Nuclear Technology, Hamburg, Germany, May 2016Suche in Google Scholar
© 2016, Carl Hanser Verlag, München
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Editorial
- Selected contributions from 1th Sino-German Symposium on Fundamentals of Advanced Nuclear Safety Technology
- Technical Contributions/Fachbeiträge
- Scientific codes developed and used at GRS – Nuclear simulation chain
- Challenges on innovations of newly-developed safety analysis codes
- Validation of system codes for plant application on selected experiments
- Progress of Experimental Research on Nuclear Safety in NPIC
- Severe accident research activities at Helmholtz-Zentrum Dresden-Rossendorf (HZDR)
- THAI experimental programme for containment safety assessment under severe accident conditions
- A spray cooling technique for spent fuel assembly stored in pool
- KIT multi-physics tools for the analysis of design and beyond design basis accidents of light water reactors
- Coupled neutronics/thermal-hydraulics and safety characteristics of liquid-fueled Molten Salt Reactors
- 10.3139/124.110680
- Validation of the ATHLET-SC code by trans-critical transient data
- Qualification of CFD-models for multiphase flows
- The reactor dynamics code DYN3D
- Critical flow phenomena and modeling in advanced nuclear safety technology
- 10.3139/124.110682
- Safety and security aspects in design of digital safety I&C in nuclear power plants
- Thermohydraulic safety issues for liquid metal cooled systems
- Design and safety analysis of the helium cooled solid breeder blanket for CFETR
- Qualification of pebble fuel for HTGRs
- High temperature reactors for cogeneration applications
Artikel in diesem Heft
- Contents/Inhalt
- Contents
- Summaries/Kurzfassungen
- Summaries
- Editorial
- Selected contributions from 1th Sino-German Symposium on Fundamentals of Advanced Nuclear Safety Technology
- Technical Contributions/Fachbeiträge
- Scientific codes developed and used at GRS – Nuclear simulation chain
- Challenges on innovations of newly-developed safety analysis codes
- Validation of system codes for plant application on selected experiments
- Progress of Experimental Research on Nuclear Safety in NPIC
- Severe accident research activities at Helmholtz-Zentrum Dresden-Rossendorf (HZDR)
- THAI experimental programme for containment safety assessment under severe accident conditions
- A spray cooling technique for spent fuel assembly stored in pool
- KIT multi-physics tools for the analysis of design and beyond design basis accidents of light water reactors
- Coupled neutronics/thermal-hydraulics and safety characteristics of liquid-fueled Molten Salt Reactors
- 10.3139/124.110680
- Validation of the ATHLET-SC code by trans-critical transient data
- Qualification of CFD-models for multiphase flows
- The reactor dynamics code DYN3D
- Critical flow phenomena and modeling in advanced nuclear safety technology
- 10.3139/124.110682
- Safety and security aspects in design of digital safety I&C in nuclear power plants
- Thermohydraulic safety issues for liquid metal cooled systems
- Design and safety analysis of the helium cooled solid breeder blanket for CFETR
- Qualification of pebble fuel for HTGRs
- High temperature reactors for cogeneration applications
