TY - GEN
T1 - Towards Model-Based Specification and Safety Assurance of Nuclear I&C Systems
T2 - 11th International Topical Meeting on Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies, NPIC&HMIT
AU - Linnosmaa, Joonas
AU - Valkonen, Janne
AU - Karpati, Peter
AU - Hauge, André
AU - Sechi, Fabien
AU - Gran, Bjørn Axel
N1 - Conference code: 11
PY - 2019
Y1 - 2019
N2 - Complexity of modern control and safety systems challenge the usual linear document-based presentation of system design. This complicates the work of designers, assessors and regulators comprehending the system, whose understanding often depends on building a mental model of the system and thus assessing its suitability. More rigorous and structured way to represent the system, than the linear documents-based, is model-based approach. Based on a literature review, SysML and AADL were identified as suitable candidates. They were tried in an exploratory case study modelling APR1400 reactor protection system, based on its linear description from a real applicant’s design control document. Effort was also taken to extract safety assurance information (for independence) from the documentation and organize it into a structured safety argument. Research serves also to discuss the strengths and weaknesses of model-based specification and assessment compared to document-based approaches. Modelling of the system based on design document and extracting safety assurance information was challenging. Results, based on the modelling experiences and literature review, argue that the studied architecture languages offer benefits over the use of natural language in clarity, ambiguity and traceability. However, using these architecture description languages require extensive modelling expertise and effort to allow a smooth modelling process and understanding. In addition, multidisciplinary insight into the system at both the conceptual level as well as hardware and software level is required. We also identified support of classical safety analysis methods within SysML and AADL.
AB - Complexity of modern control and safety systems challenge the usual linear document-based presentation of system design. This complicates the work of designers, assessors and regulators comprehending the system, whose understanding often depends on building a mental model of the system and thus assessing its suitability. More rigorous and structured way to represent the system, than the linear documents-based, is model-based approach. Based on a literature review, SysML and AADL were identified as suitable candidates. They were tried in an exploratory case study modelling APR1400 reactor protection system, based on its linear description from a real applicant’s design control document. Effort was also taken to extract safety assurance information (for independence) from the documentation and organize it into a structured safety argument. Research serves also to discuss the strengths and weaknesses of model-based specification and assessment compared to document-based approaches. Modelling of the system based on design document and extracting safety assurance information was challenging. Results, based on the modelling experiences and literature review, argue that the studied architecture languages offer benefits over the use of natural language in clarity, ambiguity and traceability. However, using these architecture description languages require extensive modelling expertise and effort to allow a smooth modelling process and understanding. In addition, multidisciplinary insight into the system at both the conceptual level as well as hardware and software level is required. We also identified support of classical safety analysis methods within SysML and AADL.
KW - architecture description language
KW - model-based systems engineering
KW - safety critical systems
KW - literature review
UR - https://www.scopus.com/pages/publications/85071027139
M3 - Conference article in proceedings
SP - 276
EP - 289
BT - 11th Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies
PB - American Nuclear Society (ANS)
Y2 - 9 February 2019 through 14 February 2019
ER -