• Title/Summary/Keyword: Nuclear Safety Software

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Development of Software Development Methodology with Aspect of Railway Safety (안전을 고려한 철도소프트웨어 개발방법론 도출방안 연구)

  • Joung, Eui-Jin;Shin, Kyung-Ho
    • Proceedings of the KIEE Conference
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    • 2007.10c
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    • pp.201-203
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    • 2007
  • Safety critical systems are those in which a failure can have serious and irreversible consequences. Nowadays digital technology has been rapidly applied to critical system such as railways, airplanes, nuclear power plants, vehicles. The main difference between analog system and digital system is that the software is the key component of the digital system. The digital system performs more varying and highly complex functions efficiently compared to the existing analog system because software can be flexibly designed and implemented. The flexible design make it difficult to predict the software failures. This paper reviews safety standard and criteria for safety critical system such as railway system and suggests software development methodology for more detail description.

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Soil sampling plan for Analysis of Nuclear Facility Activities utilizing Visual Sample Plan (Visual Sample Plan을 활용한 미신고 시설 핵활동 분석 시료 채취 계획)

  • Su-Hui Park;Ji-Young Han;Je-Wan Park;Yong-Min Kim
    • Journal of Radiation Industry
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    • v.18 no.1
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    • pp.15-21
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    • 2024
  • The Non-Proliferation Treaty (NPT) is the basis of global efforts to prevent the spread of nuclear weapons. In Republic of Korea, safety measures are integrated with NPT approval through agreements with the International Atomic Energy Agency (IAEA) and the Safeguards Agreement. In contrast, Democratic People's Republic of Korea (DPRK), initially an NPT member, withdrew, refusing IAEA nuclear inspections. This inhibits the precise management of DPRK's nuclear facilities and limits access to related information. The Korean Peninsula, politically divided, sees DPRK in control of nuclear weapons. Although the IAEA periodically evaluates DPRK's nuclear facilities, there's a research gap in contamination and site management with nuclear activities. Recognizing the presence or absence of such activities is crucial for peaceful nuclear endeavors. This proposal suggests the number and locations for environmental sample collection using the Visual Sample Plan (VSP) software for nuclear activity analysis. VSP software is sample collection locations and quantities through statistical tests on collected data, ensuring reliability for decision-making. The proposal identifies sites and facilities for nuclear activity analysis based on IAEA safety reports, utilizing the software's embedded methods. Suggested sampling locations for undisclosed nuclear activities employ VSP's embedded techniques, including 'Show that at least some high % of the sampling area is acceptable' to confirm contamination and 'Estimate the Mean' to evaluate the average contamination level.

The C Language Auto-generation of Reactor Trip Logic Caused by Steam Generator Water Level Using CASE Tools

  • Kim, Jang-Yeol;Lee, Jang-Soo
    • Nuclear Engineering and Technology
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    • v.31 no.1
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    • pp.58-67
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    • 1999
  • The purpose is to produce a model of nuclear reactor trip logic caused by the steam generator water level of Wolsong 2/3/4 unit through an activity chart and a statechart and to produce C language automatically using Statechart-based Formalism and Stalemate MAGNUM toolset suggested by David Harel Formalism. It was worth attempting auto-generation of C language though we manually made Software Requirement Specification(SRS) for safety-critical software using statechart-based formalism. Most of the phases of the software life-cycle except the software requirement specification of an analysis phase were generated automatically by Computer Aided Software Engineering (CASE) tools. It was verified that automatically produced C language has high productivity, portability, and quality through the simulation.

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THE DEVELOPMENT OF A SAFETY ASSESSMENT APPROACH AND ITS IMPLICATION ON THE ADVANCED NUCLEAR FUEL CYCLE

  • Hwang, Yong-Soo;Kang, Chul-Hyung
    • Nuclear Engineering and Technology
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    • v.42 no.1
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    • pp.37-46
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    • 2010
  • The development of advanced nuclear fuel cycle(ANFC) technology is essential to meet the national mission for energy independence via a nuclear option in Korea. The action target is to develop environmentally friendly, cost-effective measures to reduce the burden of long term disposal. The proper scenarios regarding potential radionuclide release from a repository have been developed in this study based on the advanced korean Reference Disposal System(A-KRS). To predict safety for the various scenarios, a new assessment code based on the GoldSim software has also been developed. Deterministic analysis indicates an environmental benefit from the ANFC as long as the solid waster from the ANFC act as a proper barrier.