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Identification of Risk-Significant Components in Nuclear Power Plants to Reduce Cs-137 Radioactive Risk

Cho, Jaehyun; Han, Sang Hoon

ArticleIssue Date2021CitationRELIABILITY ENGINEERING & SYSTEM SAFETY, v.211PublisherELSEVIER SCI LTD
Power maximization method for land-transportable fully passive lead-bismuth cooled small modular reactor systems

Cho, Jaehyun; Shin, Yong-Hoon; Hwang, Il Soon

ArticleIssue Date2015CitationNUCLEAR ENGINEERING AND DESIGN, v.289, pp 240 - 251PublisherELSEVIER SCIENCE SA
Development of a Bayesian belief network model for the software reliability assessment of nuclear digital I&C safety systems

Kang, H.G.; Lee, S.H.; Lee, S.J.; Chu, T.-L.; Varuttamaseni, A.; Yue, M.; Yang, S.; Eom, H.S.; Cho, J.; Li, M.

ArticleIssue Date2017Citation10th International Topical Meeting on Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies, NPIC and HMIT 2017, v.2017, pp 796 - 805PublisherAmerican Nuclear Society
Application of a Bayesian belief network model to reliability assessment of nuclear safety-related software

Lee, S.J.; Lee, S.H.; Kang, H.G.; Chu, T.-L.; Varuttamaseni, A.; Yue, M.; Eom, H.S.; Cho, J.; Li, M.

ArticleIssue Date2017Citation10th International Topical Meeting on Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies, NPIC and HMIT 2017, v.2017, pp 806 - 813PublisherAmerican Nuclear Society
Test based reliability assessment method for a safety critical software in reactor protection system

Shin, S.M.; Cho, J.; Jung, W.; Lee, S.J.

ArticleIssue Date2017Citation10th International Topical Meeting on Nuclear Plant Instrumentation, Control, and Human-Machine Interface Technologies, NPIC and HMIT 2017, v.2017, pp 1369 - 1376PublisherAmerican Nuclear Society
Investigation of a Domain-Specific Culture Shared by Operator Groups in Nuclear Power Plants

Cho, J.; Shin, S.K.; Park, J.

ArticleIssue Date2021CitationProceedings of the 31st European Safety and Reliability Conference, ESREL 2021, pp 2753 - 2760PublisherResearch Publishing, Singapore
Treatment of expert opinion diversity in Bayesian belief network model for nuclear digital I&C safety software reliability assessment

Li, M.; Kang, H.G.; Lee, S.H.; Lee, S.J.; Chu, T.-L.; Varuttamaseni, A.; Yue, M.; Cho, J.

ArticleIssue Date2017CitationInternational Topical Meeting on Probabilistic Safety Assessment and Analysis, PSA 2017, v.1, pp 551 - 558PublisherAmerican Nuclear Society
Estimation of Plant Conditions and Environmental Impacts during Severe AccidentGo to Link

Bang, Y.S.; Kim, K.Y.; Lee, S.W.; Shin, S.E.; Cho, J.; Park, J.H.

ArticleIssue Date2022CitationTransactions of the American Nuclear Society, v.127, no.1, pp 404 - 407PublisherAmerican Nuclear Society
Explaining AI Models in Operation Support Systems with Layer-wise Relevance PropagationGo to Link

Kim, S.G.; Cho, J.

ArticleIssue Date2021CitationTransactions of the American Nuclear Society, v.125, no.1, pp 270 - 273PublisherAmerican Nuclear Society
An additively manufactured manifold-microchannel heat sink for high-heat flux cooling

Kong, D.; Jung, E.; Kim, Y.; Manepalli, V.V.; Rah, K.J.; Kim, H.S.; Hong, Y.; Choi, H.G.; Agonafer, D.; Lee, H.

ArticleIssue Date2023CitationInternational Journal of Mechanical Sciences, v.248PublisherElsevier Ltd
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