Risk-Informed Approach to Functional Safety Assessment of Instrumentation and Control Systems of Reactor Protection Systems – A Systematic Mapping Study

Anton Korolev, Alexey Tribelev

Abstract


The safety of nuclear power plants (NPPs) is achieved through the implementation of a multi-layered protection system and safety functions, tailored to the configuration of the nuclear facility. One of the critical systems in ensuring safety is the reactor protection system, which ensures the automatic transition of the reactor to a controlled safe state during emergency situations and in the event of deviations from normal operating conditions. An effective assessment of the functional safety of reactor protection systems during the design, implementation, and operation phases serves as a vital tool for confirming compliance with safety requirements and ensuring reliable protection of NPPs.

In contemporary contexts, the evaluation of functional safety effectiveness is conducted based on a risk-oriented approach, which is implemented in accordance with the regulatory requirements set forth by the IAEA and national regulatory bodies.

This article presents a systematic study that investigates the risk-oriented approach to assessing the functional safety of reactor protection systems in NPPs. The research is grounded in a systematic mapping of findings from a sample of 72 articles, selected according to predefined criteria. Consequently, the current state of the field has been defined, and key methodologies, methods, and tools have been identified. Additionally, significant trends have been highlighted, including the integration of modern modeling techniques with traditional approaches. Furthermore, areas for growth and promising directions for future research have been identified, as noted in the reviewed articles.


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References


IAEA Safety Standards. Safety of Nuclear Power Plants: Design. Specific Safety Requirements. Series No. SSR-2/1 (Rev.1), 2016

NP-001-15: Federal Rules and Regulations in the field of Atomic Energy Use. General Provisions for Nuclear Power Plant Safety Assurance, Federal Service for Environmental, Technological and Nuclear Supervision, 2016. - 55p.

IEC 61513: Nuclear power plants - Instrumentation and control for systems important to safety - General requirements for systems = - Geneva: International Electrotechnical Commission, 2011. - 148 p.

IAEA Safety standard. Safety of Nuclear Fuel Cycle Facilities. Specific Safety Requirements. Series No. SSR-4., 2017

IEC 61508:2010: Functional safety of electrical/electronic/programmable electronic safety-related systems. - Geneva : International Electrotechnical Commission, 2010.

US NRC Regulatory Guide 1.174, An Approach for Using Probabilistic Risk Assessment in Risk-Informed Decisions on Plant-Specific Changes to the Licensing Basis. - Washington, DC : U.S. Nuclear Regulatory Commission, 2011

NP-082-18 Requirements to the content and form of the safety analysis report for nuclear power plants (Requirements for Probabilistic Safety Analysis), The Federal Service for Environmental, Technological and Nuclear Supervision (Rostekhnadzor), 2018

Morozov V.B. Improvement of models and methods for probabilistic safety analysis of NPP and their application in the design and operation on NPP with VVER reactors: 05.14.03 / Morozov V.B., Moscow, 2020

Putilov A.V., Mokshin M. Yu. Predictive analysis of the sustainable development of a two-component nuclear power industry, Sustainable Innovative Development: Design and Management. 2023. Vol. 19, No. 2 (59). pp. 27-31, 2023

K. Petersen, R. Feldt, S. Mujtaba, and M. Mattsson, “Systematic mapping studies in software engineering,” in 12th international conference on evaluation and assessment in software engineering, vol. 17, no. 1/sn, 01.06.2008, pp. 1–10, DOI:10.14236/ewic/EASE2008.8

Ibrahim Ahmed, Enrico Zio, Gyunyoung Heo, Risk-informed approach to the safety improvement of the reactor protection system of the AGN-201K research reactor, Nuclear Engineering and Technology,Vo. 52, Is. 4, April 2020, pp. 764-775, DOI:10.1016/j.net.2019.09.015

Y. Bulba, Y. Ponochovny, V. Sklyar, A. Ivasiuk Classification and Research of the Reactor Protection Instrumentation and Control System Functional Safety Markov Models in a Normal Operation Mode, ICTERI 2016, Kyiv, Ukraine, June 21-24, 2016, pp.308-321

D. -A. Lee, J. Yoo and J. -S. Lee, Guidelines for the Use of Function Block Diagram in Reactor Protection Systems, 21st Asia-Pacific Software Engineering Conference, Jeju, Korea (South), 01.04.2014, pp. 135-142, DOI:10.1109/APSEC.2014.29

Verrastro, Claudio & Estryk, D.S. & Rodriguez, G.F. & Ferrucci, Franco & Alarcón, J.E. & Ríos, G.E. & Lee, J.J.. FPGA Based Reactor Protection System Architecture, 16th IGORR 2014/IAEA Technical Meeting, November 2014

Kazimierz T. Kosmowski Human Factors in Designing the Instrumentation and Control Systems Important to Safety, International Journal of Performability Engineering, 18.09.2014, Vol. 10, Iss. 7, pp.741-753

Ma, Z., Yoshikawa, H., & Yang, M. Reliability model of the digital reactor protection system considering the repair time and common cause failure. Journal of Nuclear Science and Technology, 21.01.2017, 54(5), 539–551, DOI:10.1080/00223131.2017.1291375

Muta, H., & Muramatsu, K. Quantitative modeling of digital reactor protection system using Markov state-transition model. Journal of Nuclear Science and Technology, 17.03.2024, 51(9), 1073–108, DOI:10.1080/00223131.2014.906331

Sejin Jung, Junbeom Yoo, Young-Jun Lee, A PLC platform-independent structural analysis on FBD programs for digital reactor protection systems, Annals of Nuclear Energy, Vol. 103, May 2017, pp. 454-469, DOI:10.1016/j.anucene.2017.02.006

Yichun Wu, Xuanxuan Shui, Yuanfeng Cai, Junyi Zhou, Zhiqiang Wu, Jianxiang Zheng, Development, verification and validation of an FPGA-based core heat removal protection system for a PWR, Nuclear Engineering and Design, Vol. 301, May 2016, pp. 311-319, DOI:10.1016/j.nucengdes.2016.03.018

A. S. Saber, M. K. Shaat, A. El-Sayed, H. Torkey and M. A. Shouman, Reliability Analysis Model of the Digital Reactor Protection System, 37th National Radio Science Conference (NRSC), Cairo, Egypt, 26.10.2020, pp. 230-239, DOI:10.1109/NRSC49500.2020.9235117

Liu, Kuanwei and Li, Zhaohua and Zhang, Binbin and Wang, Zhichao and Hu, Yuehua and Zhan, Wenhui and Yu, Zhangcheng, Research on the Impact of Maintenance Strategy for Protection and Safety Monitoring System on the Risk of Passive Nuclear Power Plants. 07.10.2024, SSRN: https://ssrn.com/abstract=4990157

Ashutosh Kabra, Manoj Kumar, G. Karmakar, P. P. Marathe and A. P. Tiwari Dependability Analysis of Proposed I&C Architecture for Safety Systems of a Large PWR, Symposium on Advances in Control & Instrumentation (SACI-2014), 24-26.11.2014, Mumbai

Marwa A. Shouman, Amany S. Saber, Mohamed K. Shaat, Ayman El-Sayed, Hanaa Torkey, A Hybrid Machine Learning Model for Reliability Evaluation of the Reactor Protection System, Alexandria Engineering Journal, Vol. 61, Iss. 9, September 2022, pp 6797-6809, DOI:10.1016/j.aej.2021.12.026

Sejin Jung, Junbeom Yoo, Young-Jun Lee, A Software Fault Tree Analysis Technique for Formal Requirement Specifications of Nuclear Reactor Protection Systems, Reliability Engineering & System Safety, Vol. 203(3), June 2020, 107064, ISSN 0951-8320, DOI:10.1016/j.ress.2020.107064

Kee-Choon Kwon, Jang-Soo Lee and Eunkyoung Jee A Framework for the Safety Assurance of Safety Software in Nuclear Power Plants, ISOFIC 2017, Gyeongju, Korea, 26-30.11..2017

Torkey, H., Saber, A.S., Shaat, M.K. et al. Bayesian belief-based model for reliability improvement of the digital reactor protection system. Nuclear Science and Technologies 31(10), 11.10.2020, DOI:10.1007/s41365-020-00814-6

Zhang, X., Yang, Hq., Yang, Jh., Deng, Xj. Forward Design of Nuclear Safety-Class DCS Based on Function Assignment and Signal New Energy Power Generation Automation and Intelligent Technology. SICPNPP 2024. Lecture Notes in Electrical Engineering, vol 1249. Springer, Singapore, 05.09.2024 DOI:10.3390/en17164063

Zequn Lin, Lingzhi Wang, Yuanfeng Cai, Fanyu Wang, Yichun Wu, Implementation of a built-in self-test for nuclear power plant FPGA-based safety-critical control systems, Annals of Nuclear Energy, Vol. 165(1), January 2022, 108644, ISSN 0306-4549, DOI:10.1016/j.anucene.2021.108644

Sejin Jung, Yoona Heo, Junbeom Yoo, A formal approach to support the identification of unsafe control actions of STPA for nuclear protection systems, Nuclear Engineering and Technology, Vol. 54(1), Iss. 5, October 2021, pp. 1635-1643, ISSN 1738-5733 DOI:10.1016/j.net.2021.10.033

R. Khalil Ur and G. Heo, Risk Informed Design of I&C Architecture for Research Reactors IEEE Transactions on Nuclear Science, vol. 62(1), pp. 293-299, 29.01.2015 DOI:10.1109/TNS.2014.2375361 DOI:10.1109/TNS.2014.2375361

K. U. Rahman, K. Jin and G. Heo, Risk-Informed Design of Hybrid I&C Architectures for Research Reactors, IEEE Transactions on Nuclear Science, vol. 63 (1), pp. 351-358, February 2016 DOI:10.1109/TNS.2015.2499779

Steven A. Arndt, Rossnyev Alvarado, Bernard Dittman and Kenneth Mott NRC technical basis for evaluation of its position on protection against common cause failure in digital systems used in nuclear power plants 10th ANS International Topical Meeting on Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies At: San Fransico, CA, pp. 2031-2045 11-15.06.2017

D Welbourne Safety critical software TN process control and nuclear power Icheme Symposium Series No. 141, 2016, pp.451-461

Lee, Joonjae & Verrastro, Claudio & Estryk, D & Rossi, F & Quesada, G & Rodriguez, G & Ramos, N. Reliability Analysis for different configuration of a TRIP Final Actuator Interface for a Protection System of a Research Reactor, International Conference on Research Reactors: Addressing Challenges and Opportunities to Ensure Effectiveness and Sustainability Buenos Aires, Argentina, November 2019

Q Z Liang, Y Guo and C H Peng A review on the research status of reliability analysis of the digital instrument and control system in NPPs, IOP Conference Series: Earth and Environmental Science, January 2020, 427(1):012018 DOI:10.1088/1755-1315/427/1/012018

Chen, L.; Fan, D.; Zheng, J.; Xie, X. Functional Safety Analysis and Design of Sensors in Robot Joint Drive System. Machines 10(5), 360 18.04.2022, DOI:10.3390/machines10050360

Ola Bäckströma, Jan Erik Holmberg, Use of IEC 61508 in Nuclear Applications Regarding Software Reliabilit, 11th International Probabilistic Safety Assessment and Management Conference & The Annual European Safety and Reliability, Helsinki, June 2012

N. Papakonstantinou and S. Sierla, Early phase fault propagation analysis of safety critical factory automation systems, IEEE 10th International Conference on Industrial Informatics, Beijing, China, June 2012, pp. 364-369, DOI:10.1109/INDIN.2012.6300856

Qingzhu Liang, Yinghao Yang, Hang Zhang, Changhong Peng, Jianchao Lu,Analysis of simplification in Markov state-based models for reliability assessment of complex safety systems, Reliability Engineering & System Safety,Vol. 221, February 2022, 108373, ISSN 0951-8320, DOI:10.1016/j.ress.2022.108373

Robert S Enzinnaa, Mariana Jockenhoevel-Barttfeldb, Yousef Abusharkhb, and Herve Bruneliere Modeling of Digital I&C and Software Common Cause Failures: Lessons Learned from PSAs of TELEPERM XS-Based Protection System Applications, PSAM 12, 2018

Dong-Ah Lee, Junbeom Yoo, Jang-Soo Lee, A systematic verification of behavioral consistency between FBD design and ANSI-C implementation using HW-CBMC,Reliability Engineering & System Safety, Vol. 120 (3), pp. 139-149, December 2013, DOI:10.1016/j.ress.2013.06.006

S. Li, J. Lou, X. Zong and S. Ma, Application of Fault Tree Analysis to the DCS Reliability of Nuclear Power Plants, IEEE 5th Advanced Information Management, Communicates, Electronic and Automation Control Conference (IMCEC), Chongqing, China,

-22.12.2022, pp. 1863-1868

Masanobu Haruhara, Hitoshi Muta, Yasuki Ohtori, Shohei Yamagishi & Shota Terayama. Proposal of uncertainty analysis methodology for L1PRA using Markov state-transition model. Journal of Nuclear Science and Technology, 61(5), pp. 921-934, December 2023, DOI:10.1080/00223131.2023.2287111

Liu, H, Liu, Z, Yang, X, Yan, S, & Chen, Z. The Safety Analysis of Multiple Method Fusion on Reactor Scram Subsystem Proceedings of the 2018 26th International Conference on Nuclear Engineering. Volume 6B: Thermal-Hydraulics and Safety Analyses. London, England. 22-26.07.2018, DOI:10.1115/ICONE26-82453

Vyacheslav Kharchenko, Yuriy Ponochovnyi Artem Boyarchuk, Anton Andrashov Multi-Fragmental Markov Models of Information and Control Systems Safety Considering Elimination of Hardware-Software Faults, Proceedings of the 15th International Conference on ICT in Education, Research and Industrial Applications. Integration, Harmonization and Knowledge Transfer. Volume II: Workshops Kherson, Ukraine, 12-15.06.2019

A.C. Torres-Echeverría, S. Martorell, H.A. Thompson, Design optimization of a safety-instrumented system based on RAMS+C addressing IEC 61508 requirements and diverse redundancy, Reliability Engineering & System Safety, Vo. 94(2), pp. 162-179, February 2009 ISSN 0951-8320 DOI:10.1016/j.ress.2008.02.010

Stefan Authen and Jan-Erik Holmberg Reliability analysis of digital systems in a probabilistic risk analysis for nuclear power plants, Nuclear Engineering and Technology, 44(5) pp.471-482 June 2012 DOI:10.5516/NET.03.2012.707

S. Martorell, M. Villamizar, I. Martón, J.F. Villanueva, S. Carlos, A.I. Sánchez, Evaluation of risk impact of changes to surveillance requirements addressing model and parameter uncertainties, Reliability Engineering & System Safety, Vol. 126 (3), pp. 153-165, June 2014, ISSN 0951-8320 DOI:10.1016/j.ress.2014.02.003

Tero Tyrväinen, Ola Bäckström, Jan-Erik Holmberg, Markus Porthin SICA – a software complexity analysis method for the failure probability estimation, Conference: 13th International Conference on Probabilistic Safety Assessment and Management (PSAM 13), Seoul, October 2016

Abiodun Ayodeji, Mokhtar Mohamed, Li Li, Antonio Di Buono, Iestyn Pierce, Hafiz Ahmed,Cyber security in the nuclear industry: A closer look at digital control systems, networks and human factors, Progress in Nuclear Energy, 161(9), 104738, May 2023, ISSN 0149-1970 DOI:10.1016/j.pnucene.2023.104738

Pan, X.; Chen, H.; Shen, A.; Zhao, D.; Su, X. A Reliability Assessment Method for Complex Systems Based on Non-Homogeneous Markov Processes. Sensors, 24, 3446 May 2024, DOI:10.3390/s24113446

Sejin Jung, Junbeom Yoo, Young-Jun Lee, A practical application of NUREG/CR-6430 software safety hazard analysis to FPGA software, Reliability Engineering & System Safety, 202(2), 107029, May 2020, ISSN 0951-8320 DOI:10.1016/j.ress.2020.107029

Dong-Ah Lee, Eui-Sub Kim, Junbeom Yoo, Quantitative measures of thoroughness of FBD simulations for PLC-based digital I&C system, Nuclear Engineering and Technology, 53 (1), June 2020, pp. 131-141, ISSN 1738-5733 DOI:10.1016/j.net.2020.06.017

Peter Bernard Ladkin Practical Statistical Evaluation of Critical Software, , University of Bielefeld and Causalis Limited Bev Littlewood, CSR, City University London, 01.03.2015

Shi, GL., Wang, JW., Zhang, ZH., Zhang, ML., Li, L. (2022). Development and Application of Self-diagnosis and Analysis Function of FirmSys. Nuclear Power Plants: Innovative Technologies for Instrumentation and Control Systems. ISNPP 2021. Lecture Notes in Electrical Engineering, 2022, vol 883. Springer 19.04.2022 https://doi.org/10.1007/978-981-19-1181-1_60

Man Cheol Kim, Carol S. Smidts, Three suggestions on the definition of terms for the safety and reliability analysis of digital systems, Reliability Engineering & System Safety, Vol. 135, pp. 81-91, March 2015, ISSN 0951-8320 DOI:10.1016/j.ress.2014.10.022

Jae-Cheon Jung, Hoon-Sun Chang and Hang-Bae KIM, “3+3 process” for safety critical software for I&C system in nuclear power plants, Nuclear engineering and technology, vol.41 No.1, February 2009

Valkonen, Janne & Björkman, Kim & Holmberg, Jan-Erik & Lahtinen, Jussi & Pakonen, Antti & Tyrväinen, Tero & Heljanko, Keijo & Kuismin, Tuomas & Wieringa, Siert. Safety evaluation and reliability analysis of nuclear automation. Presentation of the SARANA project in SAFIR2014 Interim Seminar, 21-22.03.2013.

Ola Bäckström, Jan-Erik Holmberg, Markus Porthin, Tero Tyrväinen Moding – modeling the reliability of digital I&C in modern nuclear power plants, 13th International Conference on Probabilistic Safety Assessment and Management, PSAM 13, October 2016

A.C. Torres-Echeverría, S. Martorell, H.A. Thompson, Modelling and optimization of proof testing policies for safety instrumented systems, Reliability Engineering & System Safety, Vol. 94(4), pp. 838-854, April 2009, ISSN 0951-8320 DOI:10.1016/j.ress.2008.09.006

Sejin Jung, Eui-Sub Kim, Junbeom Yoo, Jang-Yeol Kim, Jong Gyun Choi, An evaluation and acceptance of COTS software for FPGA-based controllers in NPPS, Annals of Nuclear Energy, Vol.94 (4), , pp 338-349, August 2016 ISSN 0306-4549 DOI:10.1016/j.anucene.2016.03.026

Yuanfeng Cai, Yichun Wu, Junyi Zhou, Mingxing Liu, Qing Zhang, Quantitative software reliability assessment methodology based on Bayesian belief networks and statistical testing for safety-critical software, Annals of Nuclear Energy, Volume 145, 107593, September 2020, ISSN 0306-4549 DOI:10.1016/j.anucene.2020.107593

J. Yoo, E. S. Kim, D. A. Lee, J. G. Choi, Y. J. Lee and J. S. Lee, "NuDE 2.0: A model-based software development environment for the PLC & FPGA based digital systems in nuclear power plants," 2014 International Symposium on Integrated Circuits (ISIC), Singapore, 10-12.12.2014, pp. 604-607 DOI:10.1109/ISICIR.2014.7029503

Yiliu Liu, Safety barriers: Research advances and new thoughts on theory, engineering and management, Journal of Loss Prevention in the Process Industries, Volume 67(5), 104260, August 2020, ISSN 0950-4230 DOI:10.1016/j.jlp.2020.104260

R.B.N. Vital, P.F. Frutuoso e Melo, J.A.C.C. Medeiros, M.A.B. Alvarenga, Availability assessment of a nuclear reactor limitation system by a Timed Petri Net, Progress in Nuclear Energy, Volume 152(5), 104380, October 2022, ISSN 0149-1970 DOI:10.1016/j.pnucene.2022.104380

E.-S. Kim, D.-A. Lee, S. Jung, J. Yoo, J.-G. Choi, and J.-S. Lee, “NuDE 2.0: A Formal Method-based Software Development, Verification and Safety Analysis Environment for Digital I&Cs in NPPs,” Journal of Computing Science and Engineering, vol. 11(1). pp. 9–23, 30.03.2017 DOI:10.5626/JCSE.2017.11.1.9

Darpan Krishnakumar Shukla, A. John Arul, Static and dynamic reliability studies of a fast reactor shutdown system using smart component method, Annals of Nuclear Energy, Vol. 136(1), 107011

February 2020, ISSN 0306-4549 DOI:10.1016/j.anucene.2019.107011

Kwang-Seop Son, Jae-Gu Song, Jung-Woon Lee, Development of the framework for quantitative cyber risk assessment in nuclear facilities, Nuclear Engineering and Technology, Vol.55(6), March 2023, pp. 2034-2046, ISSN 1738-5733 DOI:10.1016/j.net.2023.03.023

W. Ma, B. Wen, B. Xu, H. Yan and L. Zhou, Optimization of Reliability in ACP100 Automatic Depressurization System Squib Valve Control System," 2024 Global Reliability and Prognostics and Health Management Conference (PHM-Beijing), Beijing, China, 11-13.10.2024, pp. 1-6, doi: 10.1109/PHM-Beijing63284.

Mariana Jockenhövel-Barttfelda Stefan Karga, Christian Hesslerb and Herve Bruneliere, Reliability Analyses of Digital I&C Systems within the Verification and Validation Process, Probabilistic Safety Assessment and Management PSAM 14, 2018, Los Angeles, CA,

Kharchenko, V., Ponochovnyi, Y., Boyarchuk, A., Andrashov, A., Rudenko, I. Multi-fragmental Markov’s Models for Safety Assessment of NPP I&C System Considering Migration of Hidden Failures. Information and Communication Technologies in Education, Research, and Industrial Applications. ICTERI 2019. Communications in Computer and Information Science, vol 1175., pp.302-326 January 2020, Springer, Cham DOI:10.1007/978-3-030-39459-2_14

Wu, ZG., Zhu, J., Yu, XB. Reliability Analysis of Tripping Solenoid Valve Power System Based on Dynamic Fault Tree and Sequential Monte Carlo. Nuclear Power Plants: Innovative Technologies for Instrumentation and Control Systems. ISNPP 2021. Lecture Notes in Electrical Engineering, vol 883. April 2022, pp.148-158, Springer, Singapore DOI:10.1007/978-981-19-1181-1_14

Haruhara, M., Muta, H., Ohtori, Y., Yamagishi, S., & Terayama, S. Proposal of uncertainty analysis methodology for L1PRA using Markov state-transition model. Journal of Nuclear Science and Technology, 61(5), pp.921–934. December 2023 DOI:10.1080/00223131.2023.2287111

Junbeom Yoo, Eui-Sub Kim2, Dong Ah Lee3, and Jong-Gyun Choi An Integrated Software Development Framework for PLC & FPGA based Digital I&Cs, ISOFIC/ISSNP 2014, Jeju, Korea, 24-28.08.2014

Phillip McNelles, Zhao Chang Zeng, Guna Renganathan, Greg Lamarre, Yolande Akl, Lixuan Lu, A comparison of Fault Trees and the Dynamic Flowgraph Methodology for the analysis of FPGA-based safety systems Part 1: Reactor trip logic loop reliability analysis, Reliability Engineering & System Safety, Vol. 153(5), May 2016, pp. 135-150, ISSN 0951-8320 DOI:10.1016/j.ress.2016.04.014

E. Nouri, N. Nosrati, H. T. Asl, M. R. Manavand and Z. Navabi, "Multi-Level Fault Injection Methodology Using UVM-SystemC," 2023 IEEE East-West Design & Test Symposium (EWDTS), Batumi, Georgia, September 2023, pp. 1-6 DOI:10.1109/EWDTS59469.2023.10297034

Xi, CH., Sun, W., Zhang, LM. The Software Modeling and Sensitivity Study of Computer Based I&C System in Probabilistic Safety Assessment of Nuclear Power Plant. Nuclear Power Plants: Innovative Technologies for Instrumentation and Control Systems. ISNPP 2021. Lecture Notes in Electrical Engineering, vol 883. pp.97-103 19.04.2022, ,Springer, Singapore DOI: 10.1007/978-981-19-1181-1_10

Lin, YJ., Yang, JM., Wang, RY., Yang, YX. Research on Common Cause Fault Evaluation Model of RTS Based on β-factor Method. Nuclear Power Plants: Innovative Technologies for Instrumentation and Control Systems. ISNPP 2021. Lecture Notes in Electrical Engineering, vol 883. pp.590-599, Springer, Singapore 19.04.2022, DOI:10.1007/978-981-19-1181-1_57

Athira Varma Jayakumar, Systematic Model-based Design Assurance and Property-based Fault Injection for Safety Critical Digital, Virginia Commonwealth University, Richmond, Virginia, 2020

H. Tu, L. Yao, X. W. Zhai, C. Gui and X. Fan, Reliability Test Method of Nuclear Power DCS Network Communication Based on Fault Injection," 2023 8th International Conference on Computer and Communication Systems (ICCCS), Guangzhou, China, 21-23.04.2023 doi: 10.1109/ICCCS57501.2023.10150497.

Y. Nakata et al., "Model-based fault injection for failure effect analysis — Evaluation of dependable SRAM for vehicle control units," IEEE/IFIP 41st International Conference on Dependable Systems and Networks Workshops (DSN-W), Hong Kong, China, June 2011 DOI:10.1109/DSNW.2011.5958842

Yasuo Sugure, Yasuhiro Ito, Yohei Nakata, Yusuke Takeuchi, Hiroshi Kawaguchi, Masahiko Yoshimoto, Shigeru Oho, Failure Modes and Effects Analysis Using Virtual Prototyping System with Microcontroller Model for Automotive Control System, IFAC Proceedings Volumes, Advances in Automotive Control Volume 46(21), September 2013, pp. 562-563, ISSN 1474-6670, ISBN 9783902823489 DOI:10.3182/20130904-4-JP-2042.00103

PLCopen TC6. Guidelines for the use of PLCs in safety-related applications. PLCopen, 2015

IEC 60880. Software for computers in the safety systems of nuclear power plants. International Electrotechnical Commission, 2013.

ERPI NP-5652/TR-1025243. Guidelines for the use of software in safety-related systems. ERPI, 2010.

SanPiN 2.6.1.2523-09. Radiation Safety Standards (NRB-99/2009). Approved by the decree of the Chief State Sanitary Doctor of the Russian Federation dated December 30, 2009, No. 58


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