An Integrated Risk Assessment Process of Safety-Related Digital I&amp;C Systems in Nuclear Power Plants

Zhang, Hongbin; Bao, Han; Shorthill, Tate; Quinn, Edward

doi:10.1080/00295450.2022.2076486

Cited by 6 publications

(5 citation statements)

References 10 publications

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“…The hybrid method provides a means to overcome limitations of conventional methods. A formalized process that relies on the modified BFM and PBF-2 is shown in Figure 47, which has been demonstrated in [28] [92]. The subsequent section will demonstrate this process as with a case study.…”

Section: A Modified Beta-factor Methods For the Analysis Of Software ...mentioning

confidence: 97%

“…The sub-factor names alone are not sufficient for assessing each sub-factor; therefore, readers are advised to visit the original source material for scoring guidance. Beta, given by Equation (28), is a function of the assigned sub-factor scores and the denominator . The model was arranged such that the upper and lower limits for beta correspond with dependent failure values reported in literature [77].…”

Section: A Modified Beta-factor Methods For the Analysis Of Software ...mentioning

confidence: 99%

“…The result is R=s/m=0.5 (i.e., A+ from Table 43). Table 53 shows the sub-factor scores for the BPs of CCCG1 and the calculation for beta based on Equation (28). The BPs for CCCGs 2-5 share the same qualitative features and receive beta-factor scores of 0.123 and 0.568 for their hardware and software, respectively.…”

Section: Case Study -Rts Ccf Estimationmentioning

confidence: 99%

“…Figure 11. Workflow of the Redundant-guided System-theoretic Hazard Analysis (RESHA) in the proposed framework for the hazard analysis of DI&C systems (derived from [28]). ....17…”

mentioning

confidence: 99%

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An Integrated Framework for Risk Assessment of High Safety Significant Safety-related Digital Instrumentation and Control Systems in Nuclear Power Plants: Methodology and Demonstration

Bao

Svetlana

Park

et al. 2022

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This report documents the activities performed by Idaho National Laboratory (INL) during Fiscal Year (FY) 2022 for the U.S. Department of Energy (DOE) Light Water Reactor Sustainability (LWRS) Program, Risk Informed Systems Analysis (RISA) Pathway, digital instrumentation and control (DI&C) risk assessment project. In FY 2019, the RISA Pathway initiated a project to develop a risk assessment strategy for delivering a technical basis to support effective and secure DI&C technologies for digital upgrades/designs. A framework was proposed for this strategy, which aims to (1) provide a best-estimate, risk-informed capability to quantitatively and accurately estimate the risk impact of plant modernization, considering the introduction of high safety-significant safety-related (HSSSR) DI&C systems, (2) support and supplement existing risk-informed DI&C design guides by providing quantitative risk information and evidence, (3) offer a capability of design architecture evaluation of various DI&C systems, (4) assure the long-term safety and reliability of HSSSR DI&C systems, and (5) reduce uncertainty in costs and support integration of DI&C systems in the plant.

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Section: A Modified Beta-factor Methods For the Analysis Of Software ...mentioning

confidence: 97%

Section: A Modified Beta-factor Methods For the Analysis Of Software ...mentioning

confidence: 99%

Section: Case Study -Rts Ccf Estimationmentioning

confidence: 99%

“…Figure 11. Workflow of the Redundant-guided System-theoretic Hazard Analysis (RESHA) in the proposed framework for the hazard analysis of DI&C systems (derived from [28]). ....17…”

mentioning

confidence: 99%

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An Integrated Framework for Risk Assessment of High Safety Significant Safety-related Digital Instrumentation and Control Systems in Nuclear Power Plants: Methodology and Demonstration

Bao

Svetlana

Park

et al. 2022

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“…The abnormal core temperature distribution could lead to serious accidents such as core meltdowns, causing serious casualties and economic losses. Therefore, it is important to perform accurate and reliable anomaly detection for reactor core temperature [5][6][7][8].…”

Section: Introductionmentioning

confidence: 99%

Feature Disentangling Autoencoder for Anomaly Detection of Reactor Core Temperature with Feature Increment Strategy

Mao

et al. 2023

Processes

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Anomaly detection for core temperature has great significance in maintaining the safety of nuclear power plants. However, traditional auto-encoder-based anomaly detection methods might extract the latent space features with redundancy, which may lead to missing and false alarms. To address this problem, the idea of feature disentangling is introduced under the auto-encoder framework in this paper. First, a feature disentangling auto-encoder (DAE) is proposed where a latent space disentangling loss is designed to disentangle the features. We further propose an incrementally feature disentangling auto-encoder (IDAE), which is the improved version of DAE. In the IDAE model, an incremental feature generation strategy is developed, which enables the model to evaluate the disentangling degree to adaptively determine the feature dimension. Furthermore, an iterative training framework is designed, which focuses on the parameter training of the newly incremented feature, overcoming the difficulty of model training. Finally, we illustrate the effectiveness and superiority of the proposed method on a real nuclear reactor core temperature dataset. IDAE achieves average false alarm rates of 4.745% and 6.315%, respectively, using two monitoring statistics, and achieves average missing alarm rates of 6.4% and 2.9%, respectively, using two monitoring statistics, outperforming the other methods.

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Replacement Strategy for Aging Nuclear Power Instrumentation and Control Equipment Based on Life Margin

Chen,

Li,

Xie

et al. 2024

Nuclear Technology

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An Integrated Risk Assessment Process of Safety-Related Digital I&C Systems in Nuclear Power Plants

Cited by 6 publications

References 10 publications

An Integrated Framework for Risk Assessment of High Safety Significant Safety-related Digital Instrumentation and Control Systems in Nuclear Power Plants: Methodology and Demonstration

An Integrated Framework for Risk Assessment of High Safety Significant Safety-related Digital Instrumentation and Control Systems in Nuclear Power Plants: Methodology and Demonstration

Feature Disentangling Autoencoder for Anomaly Detection of Reactor Core Temperature with Feature Increment Strategy

Replacement Strategy for Aging Nuclear Power Instrumentation and Control Equipment Based on Life Margin

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