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US NRC, Industry-Average Performance for Components and Initiating Events at U.S. Commercial Nuclear Power Plants, NUREG/CR-6928, 2007.
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IAEA, Generic Component Reliability Data for Research Reactor PSA, IAEA-TECDOC-930, 1997.
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US NRC, Common-Cause Failure Parameter Estimations, NUREG/CR-5497, October 1998.
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6 |
US NRC, "CCF parameter estimation, 2007 Update," http://nrcoe.inl.gov/results/CCF/ParamEst2007/ccfparamest.htm, September, 2008.
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7 |
KAERI, Development of A Standard Method for Human Reliability Analysis (HRA) of Nuclear Power Plants: Level I PSA Full Power Internal HRA, KAERI/TR-2961, KAERI, 2005.
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8 |
Y. H. Lee, "Design Improvement to a Research Reactor for Safety Enhancement using PSA," J. Korean Soc. Saf., Vol. 33, No. 3, 2018.
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9 |
Y. H. Lee, "Internal Event Level 1 Probabilistic Safety Assessment for Korea Research Reactor", J. Korean Soc. Saf., Vol. 36, No. 4, 2021.
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10 |
Y. H. Lee, "Initiating Event Selection and Analysis for Probabilistic Safety Assessment of Korea Research Reactor," J. Korean Soc. Saf., Vol. 36, No. 2, 2021.
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11 |
KAERI, Analysis of Generic Common Cause Failure Event Data for Domestic Nuclear Power Plant, KAERI/TR-5296/2013, KAERI, 2013.
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12 |
KAERI, KMRR Safety Analysis Report, KAERI/TR-710/ 1996, KAERI, 2018.
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13 |
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