Reliability Analysis of Digital Systems in a Probabilistic Risk Analysis for Nuclear Power Plants

Authén, Stefan; Holmberg, Jan-Erik

doi:10.5516/net.03.2012.707

Cited by 45 publications

(26 citation statements)

References 16 publications

(16 reference statements)

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“…Different publications emphasize the relevance of the I&C system design modeling and analysis in various contexts: [4] presents an approach for the modeling of computer-based I&C systems in the context of reliability analysis for the probabilistic risk analysis, [5] likewise models I&C systems for the reliability estimation, [6], in its "3+3 Process" approach, proposes the formal modeling of software, subsequent code generation, and coverage analysis, [7] evaluates description languages with respect to the modeling of CCF and dependencies, [8] considers the modeling of physical plant processes in order to improve the control system design, and [9] promotes the model driven engineering approach for small modular reactors.…”

Section: Introductionmentioning

confidence: 99%

“…is, for example, accomplished in [4] and [5]. Several I&C system analysis techniques are stated in [2], which include the defense-in-depth and diversity (D3) analysis, fault tree analysis (FTA), event tree analysis (ETA) and failure mode and effects analysis (FMEA).…”

Section: Introductionmentioning

confidence: 99%

“…The numbering of the first life-cycle phases serves the relationship between the life-cycle and method, which is utilised in section 4 4. For this reason, the life-cycle phase of system validation solely verifies the system requirements.…”

mentioning

confidence: 99%

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Method for the Analysis of Temporal Change of Physical Structure in the Instrumentation and Control Life-Cycle

Göring

Fay

2013

Nuclear Engineering and Technology

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Section: Introductionmentioning

confidence: 99%

Section: Introductionmentioning

confidence: 99%

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Method for the Analysis of Temporal Change of Physical Structure in the Instrumentation and Control Life-Cycle

Göring

Fay

2013

Nuclear Engineering and Technology

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“…security and inter-channel communication, (3) the need for a highly integrated control room, and (4) difficulty assessing the reliability of digital I&C [2], [3]. Reliability and risk assessment was emphasized by Stefan and Jan-Erik, who concluded that the risk impact of digital systems, particularly related to software, the central processing unit (CPU), and CCFs should be calculated [4]. The cost of design is another significant concern when building research reactors, especially low power ones.…”

mentioning

confidence: 99%

Risk Informed Design of I&C Architecture for Research Reactors

Heo

2015

IEEE Trans. Nucl. Sci.

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A deterministic design philosophy for systems, structures, and components of nuclear facilities, accepted by all stakeholders, has been adopted to address safety concerns. However, over-conservatism makes the design of nuclear facilities, especially research reactors, expensive; therefore, the industry needs to reevaluate its level of over-conservatism to obtain an optimized design. This paper proposes a probabilistic design and optimization approach for instrumentation & control (I&C) systems of research reactors based on sensitivity, availability criteria, and cost. Compared to commercial nuclear power plants, research reactors are sensitive to the cost competitiveness of I&C systems, so optimization of I&C system design is needed. As a case study, we formulated four architecture configurations for a reactor protection system and performed the reliability feature analysis, assessed cost, and computed reliability index. In addition to International Electrotechnical Commission (IEC) and American Society of Mechanical Engineers (ASME) criteria, we introduce the reliability index, a novel parameter describing the correlation between cost and reliability used to determine the point at which an I&C architecture has been optimized. To observe the significance of this study, we compared our results with a benchmark architecture. Our novel probabilistic design and optimization approach produced two optimized I&C architectures with design cost reductions of 30-40% compared to the benchmark architecture, while maintaining safety and availability.Index Terms-I&C Architecture, probabilistic design approach, reliability index, research reactors, sensitivity analysis, sensitivity.

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“…Co-simulations are the hotspots of the computer simulation field, 11 which also reflect the concept of the digital nuclear power plant. 12 The driving systems of main steam and feed water isolation valves with the quick-closing function have almost the same long history as nuclear power plants. 13 The first driving system for closing the valve quickly, which was very large and electric-powered, was equipped in the first commercial nuclear power plant in the world in 1956.…”

Section: Introductionmentioning

confidence: 99%

Co-simulation design and experimental study on the hydraulic–pneumatic-powered driving system of main steam and feed water isolation valves for CAP1400

Pan

Gu²,

Guo³

et al. 2017

Advances in Mechanical Engineering

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CAP1400 is an advanced large passive nuclear power technology under research and development, and related electromechanical equipment should be improved to guarantee the safety. The driving systems of main steam and feed water isolation valves are electromechanical equipment in nuclear power plants with nonlinear systems, which are not easy to be identified with traditional mathematical models. This article presents the design process of a novel driving system of the main steam isolation valve under the emergency quick-closing situation, which do not need the mathematical models. The novel driving system, which has a symmetrical and concise structure, is designed to include only two independent hydraulic output circuits, two independent hydraulic input circuits, and a nitrogen circuit for auxiliary driving. A cosimulation method, which takes advantage of AMESim, Adams, UG, and MATLAB, was proposed to establish the models of the main steam and feed water isolation valve and the driving system. Finally, co-simulations and experimental verifications of the emergency quick-closing situations, which include two hydraulic output circuits working together for quick closing and only one hydraulic output circuit for quick closing, were provided to confirm the performances and effectiveness of the proposed driving system and co-simulation method.

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Reliability Analysis of Digital Systems in a Probabilistic Risk Analysis for Nuclear Power Plants

Cited by 45 publications

References 16 publications

Method for the Analysis of Temporal Change of Physical Structure in the Instrumentation and Control Life-Cycle

Method for the Analysis of Temporal Change of Physical Structure in the Instrumentation and Control Life-Cycle

Risk Informed Design of I&C Architecture for Research Reactors

Co-simulation design and experimental study on the hydraulic–pneumatic-powered driving system of main steam and feed water isolation valves for CAP1400

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Reliability Analysis of Digital Systems in a Probabilistic Risk Analysis for Nuclear Power Plants

Cited by 45 publications

References 16 publications

Method for the Analysis of Temporal Change of Physical Structure in the Instrumentation and Control Life-Cycle

Method for the Analysis of Temporal Change of Physical Structure in the Instrumentation and Control Life-Cycle

Risk Informed Design of I&amp;C Architecture for Research Reactors

Co-simulation design and experimental study on the hydraulic–pneumatic-powered driving system of main steam and feed water isolation valves for CAP1400

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Risk Informed Design of I&C Architecture for Research Reactors