• Journal of Convergence Society for SMB
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• v.6 no.1
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• pp.7-15
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• 2016

As most devices in a wide range of automotive, aerospace, and missile have built-in software that controls the system behaviors, the safety of the software is growing in its importance. That is, the software safety has emerged as one of big issues because the threat of accidents caused by software malfunction is rising. Accident by software can be occurred from user mal-operation, but the fundamental reason of the accident comes from insufficient verification of the safety in software development process. Therefore, this paper presents how the software safety analysis and management activities should be done in the development process. In particular, we propose how to apply the safety analysis and management activities in the prototype or incremental development process.

• Nuclear Engineering and Technology
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• v.47 no.2
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• pp.212-218
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• 2015

We describe a comparative analysis of different tools used to assess safety-critical software used in nuclear power plants. To enhance the credibility of safety assessments and to optimize safety justification costs, $Electricit{\acute{e}}$ de France (EDF) investigates the use of methods and tools for source code semantic analysis, to obtain indisputable evidence and help assessors focus on the most critical issues. EDF has been using the PolySpace tool for more than 10 years. Currently, new industrial tools based on the same formal approach, Abstract Interpretation, are available. Practical experimentation with these new tools shows that the precision obtained on one of our shutdown systems software packages is substantially improved. In the first part of this article, we present the analysis principles of the tools used in our experimentation. In the second part, we present the main characteristics of protection-system software, and why these characteristics are well adapted for the new analysis tools. In the last part, we present an overview of the results and the limitations of the tools.

• Quality Improvement in Health Care
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• v.24 no.1
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• pp.9-22
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• 2018

Purpose: The purpose of this study is to develop the Korean root cause analysis (RCA) software that can be used to systematically investigate underlying causes for preventing or reducing recurrence of patient safety incidents. Methods: We reviewed the existing guidelines and literatures on the RCA in order to figure out the RCA process. Also we examined the existing RCA softwares for investigating patient safety incidents to design the contents and interface of the RCA software. Based on the results of reviewing literatures and softwares, we developed a draft version of the Korean RCA software that can be easily used in Korean hospital settings by RCA teams. Results: The Korean RCA software consisted of several modules, which are modules for identifying patient safety incidents, organizing RCA team, collecting and analysing data, determining contributory factors and root causes, developing the action plans, and guiding evaluation. Conclusion: The Korean RCA software included optimized RCA process and structured logic for cause analysis. Thus even beginners in RCA are expected to easily use this software for investigating patient safety incidents. As software has been developed with the public financial support, it will be distributed free of charge. We hope that it will contribute to facilitating patient safety improvement activities in Korea.

• Journal of Computing Science and Engineering
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• v.11 no.1
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• pp.9-23
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• 2017

NuDE 2.0 (Nuclear Development Environment 2.0) is a formal-method-based software development, verification and safety analysis environment for safety-critical digital I&Cs implemented with programmable logic controller (PLC) and field-programmable gate array (FPGA). It simultaneously develops PLC/FPGA software implementations from one requirement/design specification and also helps most of the development, verification, and safety analysis to be performed mechanically and in sequence. The NuDE 2.0 now consists of 25 CASE tools and also includes an in-depth solution for indirect commercial off-the-shelf (COTS) software dedication of new FPGA-based digital I&Cs. We expect that the NuDE 2.0 will be widely used as a means of diversifying software design/implementation and model-based software development methodology.

• Proceedings of the KSR Conference
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• 2008.11b
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• pp.1257-1263
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• 2008

Recent advances in embedded system technology have brought more dependence on automating train control. While much efforts have been reported to improve electronic hardware's safety, not so much systematic approaches to evaluate software's safety, especially for the vital software running on board train controllers. In this paper, we have developed a software testing tool to evaluate train control system software safety, expecially "Metric Analysis" module. We have reviewed requirements in the international standards and surveyed available tools in the market. From this, we identified the S/W metric analysis module is required for software evaluation. So we have developed S/W metric analysis module for railway signaling systems.

• International Journal of Safety
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• v.3 no.1
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• pp.38-46
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• 2004

This paper introduces the software life-cycle V&V (verification and validation) tasks for the KNICS (Korea nuclear instrumentation and control system) project. The objectives of the V&V tasks are mainly to develop a programmable logic controller (PLC) for safety critical instrumentation and control (I&C) systems, and then to apply the PLC to developing the prototype of an engineered safety features-component control system (ESF-CCS) in nuclear power plants. As preparative works for the software V&V, various kinds of software plans and V&V task procedures have been developed according to the software life-cycle management. A number of software V&V tools have been adopted or developed to efficiently support the V&V tasks. The V&V techniques employed in this work include a checklist-based review and inspection, a requirement traceability analysis, formal verification, and life-cycle based software testing.

• Journal of Software Engineering Society
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• v.29 no.1
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• pp.7-12
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• 2020

As interest in functional safety has recently increased, application of functional safety standards has been required in various industrial fields. A functional safety standard is a document that defines functional safety-related activities required to prevent system malfunctions. All activities defined in this standard are required differentially according to the classification results calculated through the risk analysis and assessment of the system. In the field of domestic weapon systems, there is a manual for the development and management of weapon system software issued by the Defense Acquisition Program Administration (DAPA ). This manual requires static and dynamic analysis of software for functional safety related activities. However, the manual does not specifically address the classification activity through risk analysis and assessment as required for the preceding activities. Therefore, in this study, we analyze the problems of the manual based on the representative functional safety standards, and propose improvement plans.

• Transactions of the Korean Society of Mechanical Engineers B
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• v.37 no.12
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• pp.1175-1183
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• 2013

Even if some CFD software developers and its users think that a state-of-the-art CFD software can be used to reasonably solve at least single-phase nuclear reactor safety problems, there remain limitations and uncertainties in the calculation result. From a regulatory perspective, the Korea Institute of Nuclear Safety (KINS) is presently conducting the performance assessment of commercial CFD software for nuclear reactor safety problems. In this study, to examine the prediction performance of commercial CFD software with the porous model in the analysis of the scale-down APR (Advanced Power Reactor Plus) internal flow, a simulation was conducted with the on-board numerical models in ANSYS CFX R.14 and FLUENT R.14. It was concluded that depending on the CFD software, the internal flow distribution of the scale-down APR was locally somewhat different. Although there was a limitation in estimating the prediction performance of the commercial CFD software owing to the limited amount of measured data, CFX R.14 showed more reasonable prediction results in comparison with FLUENT R.14. Meanwhile, owing to the difference in discretization methodology, FLUENT R.14 required more computational memory than CFX R.14 for the same grid system. Therefore, the CFD software suitable to the available computational resource should be selected for massively parallel computations.

• Journal of Internet Computing and Services
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• v.20 no.3
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• pp.1-11
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• 2019

Today's software systems are becoming larger and more complicated, and the risk of accidents and failures have also grown larger. Software failures and accidents in industrial fields such as automobiles, nuclear power plants, railroad industries, etc. may lead to severe damage of property and human life. The safety-related international standards, such as IEC 61508 have been established and applied to industries for decades. The safety life cycle specified in the standards emphasize the activities to develop safety requirements through hazard and risk analysis in the early stage of software development. In this paper, we propose 'Hazard Analysis Process based on STPA using SysML' in order to ensure the safety of software at the early stage of software development. The proposed hazard analysis can be effectively performed minimizing the loss of hazard by using the BDD and the IBD of SysML to define the control structure of a system. The proposed method also improves the specification of the safety constraints(requirement) by using SD. As a result, it is possible to identify the hazard without missing and identify the hazard scenarios in detail, and safety can be sufficiently ensured in the early stage of software development.

• Nuclear Engineering and Technology
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• v.38 no.3
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• pp.259-276
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• 2006

As the use of digital systems becomes more prevalent, adequate techniques for software specification and analysis have become increasingly important in nuclear power plant (NPP) safety-critical systems. Additionally, the importance of software verification and validation (V&V) based on adequate specification has received greater emphasis in view of improving software quality. For thorough V&V of safety-critical systems, V&V should be performed throughout the software lifecycle. However, systematic V&V is difficult as it involves many manual-oriented tasks. Tool support is needed in order to more conveniently perform software V&V. In response, we developed four kinds of computer aided software engineering (CASE) tools to support system specification for a formal-based analysis according to the software lifecycle. In this work, we achieved optimized integration of each tool. The toolset, NuSEE, is an integrated environment for software specification and V&V for PLC based safety-critical systems. In accordance with the software lifecycle, NuSEE consists of NuSISRT for the concept phase, NuSRS for the requirements phase, NuSDS for the design phase and NuSCM for configuration management. It is believed that after further development our integrated environment will be a unique and promising software specification and analysis toolset that will support the entire software lifecycle for the development of PLC based NPP safety-critical systems.