• Title/Summary/Keyword: Korean Standard Nuclear Power

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Systems Engineering Approach to develop the FPGA based Cyber Security Equipment for Nuclear Power Plant

  • Kim, Jun Sung;Jung, Jae Cheon
    • Journal of the Korean Society of Systems Engineering
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    • v.14 no.2
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    • pp.73-82
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    • 2018

  • In this work, a hardware based cryptographic module for the cyber security of nuclear power plant is developed using a system engineering approach. Nuclear power plants are isolated from the Internet, but as shown in the case of Iran, Man-in-the-middle attacks (MITM) could be a threat to the safety of the nuclear facilities. This FPGA-based module does not have an operating system and it provides protection as a firewall and mitigates the cyber threats. The encryption equipment consists of an encryption module, a decryption module, and interfaces for communication between modules and systems. The Advanced Encryption Standard (AES)-128, which is formally approved as top level by U.S. National Security Agency for cryptographic algorithms, is adopted. The development of the cyber security module is implemented in two main phases: reverse engineering and re-engineering. In the reverse engineering phase, the cyber security plan and system requirements are analyzed, and the AES algorithm is decomposed into functional units. In the re-engineering phase, we model the logical architecture using Vitech CORE9 software and simulate it with the Enhanced Functional Flow Block Diagram (EFFBD), which confirms the performance improvements of the hardware-based cryptographic module as compared to software based cryptography. Following this, the Hardware description language (HDL) code is developed and tested to verify the integrity of the code. Then, the developed code is implemented on the FPGA and connected to the personal computer through Recommended Standard (RS)-232 communication to perform validation of the developed component. For the future work, the developed FPGA based encryption equipment will be verified and validated in its expected operating environment by connecting it to the Advanced power reactor (APR)-1400 simulator.

  • https://doi.org/10.14248/JKOSSE.2018.14.2.073 인용 PDF KSCI HTML

Evaluation of Human Reliability Analysis Results in Probabilistic Safety Assessment for Korea Standard Nuclear Power Plants (표준 원자력발전소 확률론적 안전성 평가의 인간 신뢰도 분석 평가)

  • 강대일;정원대;양준언
    • Journal of the Korean Society of Safety
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    • v.18 no.2
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    • pp.98-103
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    • 2003

  • Based on ASME probabilistic risk assessment (PRA) and NEI PRA peer review guidance, we evaluate a human reliability analysis (HRA) in probabilistic safety assessment (PSA) for Korea standard nuclear power plants, Ulchin Unit 3&4, to improve it performed at under design. The HRA for Ulchin Unit 3&4 is assessed as higher than Grade I based on ASME PRA standard and as higher than Grade 2 based on NEI PRA peer review guidance. The major items to be improved identified through the evaluation process are the documentation, the systematic human reliability analysis, the participitation of operators in the works and review of HRA. We suggest the guidance on the identification and qualitative screening analysis for pre-accident human errors and solve some items to be improved using the suggested guidance.

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Loss of a Main Feedwater Pump Test at 100% Power Simulation using Korean Standard Nuclear Plant Analyzer (KSNPA)

  • Jeong, Won-Sang;Kim, Shin-Whan;Sung, Kang-Sik;Seo, Jong-Tae;Lee, Sang-Keun
    • Proceedings of the Korean Nuclear Society Conference
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    • 1996.05a
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    • pp.296-302
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    • 1996

  • The Loss of a Main Feedwater Pump test at 100% Power for YGN 4 was simulated in order to verify and validate the KSNPA. The comparison of the test data with the KSNPA prediction results showed reasonable agreement in the trends of the major plant parameters. All plant control systems including NSSS and T/G control systems are properly actuated and stabilized the plant conditions to a new steady state conditions in the KSNPA. From the comparison results, the KSNPA showed its capability to simulate the LOMFP event for the Korean Standard Nuclear Power Plant.

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Evaluation of Nuclear Events and Review of Reliability Improvements of Single Point Vulnerability for Electrical Systems on Korean Standard Nuclear Power Plants (국내 표준형 원전의 사고 고장원인 분석 및 발전정지 유발 전기설비의 신뢰도 개선 방안 검토)

  • Chi, Moon-Goo;Youn, Jong-Hyun
    • Proceedings of the KIEE Conference
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    • 2009.07a
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    • pp.682_683
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    • 2009

  • 원자력안전기술원이 제공하는 원전사고고장 정보에 제시된 원전사고고장 현황에서 표준형 원전의 사례에 대하여 전기설비 관련 원인을 분석하고, 출력감발 및 불시정지를 줄이기 위하여 한수원(주)이 수행하는 발전정지유발 전기설비에 대한 신뢰도 개선 방안에 대하여 기술한다.

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