References
- M. HASSAN and W. E. VESELY, “Digital I&C Systems in Nuclear Power Plants: Risk-Screening of Environmental Stressors and a Comparison of Hardware Unavailability with an Existing Analog System,” NUREG/CR-6579, Brookhaven National Laboratory (1998).
- NATIONAL RESEARCH COUNCIL, Digital Instrumentation and Control Systems in Nuclear Power Plants: Safety and Reliability Issues, National Academies Press (1997).
- D. LEE and I. KIM, “Application of Digital Technology for the Plant Protection System in Ulchin Nuclear Plant Units 5 and 6,” presented at the 2006 Int. Congress Advanced Nuclear Power Plants, Reno, Nevada, June 4–8, 2006.
- H. G. KANG et al., “The Common Cause Failure Probability Analysis on the Hardware of the Digital Protection System in Korean Standard Nuclear Power Plant,” KAERI/TR-2908/2005, Korea Atomic Energy Research Institute (2005).
- Code of Federal Regulations, Title 10, “Energy,” Part 50.55a, “General Design Criteria for Nuclear Power Plants,” U.S. Nuclear Regulatory Commission (2001).
- L. SHI et al., “Probabilistic Risk Assessments of Digital I&C in Nuclear Power Plant,” presented at the 10th Probabilistic Safety Assessment Management Conf., Seattle, Washington, June 7–11, 2010.
- H. G. KANG and T. SUNG, “An Analysis of Safety-Critical Digital Systems for Risk-Informed Design,” Reliab. Eng. Syst. Saf., 78, 3, 307 (2002); http://dx.doi.org/10.1016/S0951-8320(02)00176-X.
- P. H. SEONG, Reliability and Risk Issues in Large Scale Safety-Critical Digital Control Systems, Springer-Verlag, London (2009).
- M. R. LYU, Handbook of Software Reliability Engineering, McGraw-Hill, New York (1996).
- M. C. KIM, S. C. JANG, and J. HA, “Possibilities and Limitations of Applying Software Reliability Growth Models to Safety Critical Software,” Nucl. Eng. Technol., 39, 145 (2007); http://dx.doi.org/10.5516/NET.2007.39.2.129.
- N. FENTON et al., “Predicting Software Defects in Varying Development Lifecycles Using Bayesian Nets,” Inf. Software Technol., 49, 32 (2007); http://dx.doi.org/10.1016/j.infsof.2006.09.001.
- H. S. EOM et al., “V&V-Based Remaining Fault Estimation Model for Safety-Critical Software of a Nuclear Power Plant,” Ann. Nucl. Energy, 51, 38 (2013); http://dx.doi.org/10.1016/j.anucene.2012.06.030.
- H. G. KANG et al., “Development of a Bayesian Belief Network Model for Software Reliability Quantification of Digital Protection Systems in Nuclear Power Plants,” Ann. Nucl. Energy, 120, 62 (2018); http://dx.doi.org/10.1016/j.anucene.2018.04.045.
- J. MAY, G. HUGHES, and A. D. LUNN, “Reliability Estimation from Appropriate Testing of Plant Protection Software,” Software Eng. J., 10, 206 (1995); http://dx.doi.org/10.1049/sej.1995.0026.
- T. L. CHU et al., “Development of Quantitative Software Reliability Models for Digital Protection Systems of Nuclear Power Plants,” NUREG/CR-7044, U.S. Nuclear Regulatory Commission (2013).
- H. G. KANG et al., “Input-Profile-Based Software Failure Probability Quantification for Safety Signal Generation Systems,” Reliab. Eng. Syst. Saf., 94, 1542 (2009); http://dx.doi.org/10.1016/j.ress.2009.02.018.
- S. M. SHIN et al., “Test Based Reliability Assessment Method for a Safety Critical Software in Reactor Protection System,” presented at the 10th Int. Topl. Mtg. Nuclear Plant Instrumentation and Control and Human Machine Interface Technology (NPIC&HMIT 2017), San Francisco, California, June 11–15, 2017.
- N. Y. LEE et al., “Software Reliability Evaluation of Digital Plant Protection System Development Process Using V&V,” Proc. Korean Nucl. Soc. Spring Mtg. 2001, Cheju, Korea, May 2001.
- Y. ZHANG, “Reliability Quantification of Nuclear Safety-Related Software,” PhD Thesis, Department of Nuclear Engineering, Massachusetts Institute of Technology (2004).
- J. CHO et al., “Exhaustive Test Cases for the Software Reliability of Safety-Critical Digital Systems in Nuclear Power Plants,” Nucl. Eng. Des., 352, 110151 (2019); http://doi.org/10.1016/j.nucengdes.2019.110151.
- C. V. RAMAMOORTHY and W. T. TSAI, “Advances in Software Engineering,” Computer, 29, 47 (1996); http://dx.doi.org/10.1109/2.539720.
- S. M. SHIN et al., “Test Based Reliability Quantification Method for a Safety Critical Software Using Finite Test Cases,” presented at the 9th Int. Topl. Mtg. Nuclear Plant Instrumentation and Control and Human Machine Interface Technology (NPIC & HMIT 2015), Charlotte, North Carolina, February 22–26, 2015.
- “Core Knowledge on Instrumentation and Control Systems in Nuclear Power Plants,” IAEA NES NP-T-3.12, International Atomic Energy Agency (Dec. 2011).
- J. PALOMAR and R. WYMAN, “The Programmable Logic Controller and Its Application in Nuclear Reactor Systems,” NUREG/CR-6090, U.S. Nuclear Regulatory Commission (1993).
- “Programmable Controllers—Part 3: Programming Languages,” IEC 61131-3:2013, International Electrotechnical Commission (2013).
- M. K. LEE, S. W. SONG, and D. H. YUN, “Development and Application of POSAFE-Q PLC Platform,” presented at the 3rd Int. Conf. on Nuclear Power Plant Life Management and Long Term Operation, Salt Lake City, Utah, May 14–18, 2012.
- “SPACE, Engineering System of Teleperm XS PLC,” KWU NLL1-1026-76-V1.0/11.96, Siemens, München, Germany (1996).
- “Teleperm XS, Brief Description,” KWU NLL1-1004-76-V2.2/04.98, Siemens, München, Germany (1998).
- Tristation 1131 Developer’s Workbench: Developer’s Guide Tristation 1131, Version 4.1, Invensys, London (2006).
- J. YOO, S. CHA, and E. JEE, “A Verification Framework for FBD Based Software in Nuclear Power Plants,” presented at the 15th Asian-Pacific Software Engineering Conf., Beijing, China, December 3–5, 2008.
- W. BOLTON, Programmable Logic Controllers, Newnes, Boston, Massachusetts (2009).
- C. L. HEITMEYER, R. D. JEFFORDS, and B. G. LABAW, “Automated Consistency Checking of Requirements Specifications,” ACM Trans. Software Eng. Methodol., 5, 3, 231 (1996); http://dx.doi.org/10.1145/234426.234431.
- J. YOO et al., “A Formal Software Requirements Specification Method for Digital Nuclear Plant Protection Systems,” J. Syst. Software, 74, 1, 73 (2005); http://dx.doi.org/10.1016/j.jss.2003.10.018.
- J. YOO, E. JEE, and S. CHA, “Formal Modelling and Verification of Safety-Critical Software,” IEEE Software, 26, 3, 42 (2009); http://dx.doi.org/10.1109/MS.2009.67.
- T. L. CHU et al., “Review of Quantitative Software Reliability Methods,” BNL-94047-2010, Brookhaven National Laboratory (2010).
- G. DAHLL, B. LIWANG, and U. PULKKINEN, “Software-Based System Reliability,” NEA/SEN/SIN/WGRISK(2007)1, Working Group on Risk Assessment of the Nuclear Energy Agency, Paris, France (2007).
- S. BROWN, “Overview of IEC 61508. Design of Electrical/Electronic/Programmable Electronic Safety-Related Systems,” Comput. Control Eng. J., 11, 1, 6 (2000); http://dx.doi.org/10.1049/cce:20000101.
- “Functional Safety of Electrical/Electronic/Programmable Electronic Safety-Related Systems—Part 3: Software Requirements,” IEC 61508-3:2010, International Electrotechnical Commission (2010).
- S. REID, The New Software Testing Standard, in Achieving Systems Safety, Springer, London (2012).
- “Software and Systems Engineering—Software Testing—Part 4: Test Techniques,” ISO/IEC/IEEE 29119-4:2015, International Organization for Standardization (2015).
- “Test Documentation for Digital Computer Software Used in Safety Systems of Nuclear Power Plants,” RG1.170 Rev. 1, U.S. Nuclear Regulatory Commission (2013).
- G. G. PRECKSHOT and J. A. SCOTT, “A Proposed Acceptance Process for Commercial Off-the-Shelf (COTS) Software in Reactor Applications,” NUREG/CR-6421, U.S. Nuclear Regulatory Commission (1996).
- T. L. CHU et al., “Traditional Probabilistic Risk Assessment Methods for Digital Systems,” NUREG/CR-6962, U.S. Nuclear Regulatory Commission (2008).
- “Guidance for Evaluation of Diversity and Defense-In-Depth in Digital Computer-Based Instrumentation and Control Systems,” BTP7-19 Rev. 5, U.S. Nuclear Regulatory Commission (2007).
- R. C. BRYCE et al., “Combinatorial Testing,” Handbook of Research on Software Engineering and Productivity Technologies: Implications of Globalization, IGI Global, Hershey, Pennsylvania (2010).
- M. B. COHEN and S. UR, “Combinatorial Test Design in Practice,” presented at the 32nd ACM/IEEE Int. Conf. on Software Engineering, Cape Town, South Africa, May 1–8, 2010.
- “Use of Probabilistic Risk Assessment Methods in Nuclear Regulatory Activities; Final Policy Statement,” Fed. Regist., 60, 42622 (1995).
- K. C. KWON and M. S. LEE, “Technical Review on the Localized Digital Instrumentation and Control Systems,” Nucl. Eng. Technol., 41, 447 (2009); http://dx.doi.org/10.5516/NET.2009.41.4.447.
- J. H. PARK, D. Y. LEE, and C. H. KIM, “Development of KNICS RPS Prototype,” Proc. ISOFIC 2005, Tongyeong, Republic of Korea (2005).
- “RPS Functional Requirement Specification,” KNICS-RPS-DS101 Rev. 02, Doosan Heavy Industries and Construction Co., Ltd. (2006).
- “BP SDS for Reactor Protection System,” KNICS-RPS-SDS231 Rev. 03, Doosan Heavy Industries and Construction Co., Ltd. (2008).
- K.-C. KWON, D.-Y. LEE, and J.-G. CHOI, “Software Qualification for Digital Safety System in KNICS Project,” presented at the 3rd Int. Conf. on Nuclear Power Plant Life Management and Long Term Operation, Salt Lake City, Utah (2012).
- Guidelines for Chemical Process Quantitative Risk Analysis, Center for Chemical Process Safety/AIChE, New York (2000).
- S. H. LEE et al., “Exhaustive Testing of Safety-Critical Software for Reactor Protection System,” Reliab. Eng. Syst. Saf., 193, 106667 (2020); http://dx.doi.org/10.1016/j.ress.2019.106667.
- S. H. LEE et al., “Development of Simulation-Based Testing Environment for Safety-Critical Software,” Nucl. Eng. Technol., 50, 570 (2018); http://dx.doi.org/10.1016/j.net.2018.02.007.
- “Safety I&C System,” APR1400-Z-J-NR-14001-NP, Rev.0, KEPCO & KHNP (2014).
- J. JUNG and I. AHMED, “Development of Field Programmable Gate Array–Based Reactor Trip Functions Using Systems Engineering Approach,” Nucl. Eng. Technol., 48, 4, 1047 (2016); http://dx.doi.org/10.1016/j.net.2016.02.011.
- S. H. HAN, H. G. LIM, and S. C. JANG, “AIMS PSA: A Software for Integrating Various Types of PSAs,” presented at the 9th Probabilistic Safety Assessment Management (PSAM9), Hong Kong, China, May 18–23, 2008.
- W. S. JUNG, S. H. HAN, and J. J. HA, “An Overview of the Fault Tree Solver FTREX,” presented at the 13th Int. Conf. on Nuclear Engineering, Beijing, China, May 16–20, 2005.