1. An assessment of uncertainty on a LOFT L2–5 LBLOCA PCT Based on the ACE-RSM Approach: Complementary Work for the OECD BEMUSE Phase-III Program;Ahn;Nucl. Eng. Technol.,2010
2. The Plant-specific Uncertainty Analysis for an Ex-vessel Steam Explosion-induced Pressure Loads using a TEXAS-SAUNA Coupled System;Ahn;Nucl. Eng. Des.,2012
3. Ahn, K.I., 2019. Establishment of Best Practice for Uncertainty and Sensitivity Analyses in the Realm of Severe Accident Analysis and Development of Relevant TECDOC. 1st RCM on Advancing the State-of-Practice in Uncertainty and Sensitivity Methodologies for Severe Accident Analysis in Water Cooled Reactors, IAEA Headquarters, Vienna, Austria. 14-17 October
4. Estimation of fission product source terms for the ISLOCA of a reference PWR plant using MELCOR and MAAP5;Ahn;Nucl. Eng. Des.,2020
5. Estimation of fission product source terms for the SGTR accident of a reference PWR plant using MELCOR and MAAP5;Ahn;Nucl. Eng. Des.,2021