M. Lee

A critical heat flux approach for square rod bundles using the 1995 Groeneveld CHF table and bundle data of heat transfer research facility

M. Lee, 2000 .

Analysis of a Large-Scale PWR In-Vessel Retention Device

M. Lee, Fei-Jan Tsai, 2018, Nuclear Technology.

Uncertainty Quantification Using the MAAP5 Code of In-Vessel Hydrogen Generation in a Severe Accident at an Advanced Boiling Water Reactor

M. Lee, Te-Chuan Wang, 2020, Nuclear Technology.

A novel approach for critical heat flux enhancement during severe accident mitigation with removal of radioactive materials from the coolant

Y. Jeong, Jun-Yeop Lee, M. Lee, 2020 .

The Past, Present and Future of Nuclear Power in Taiwan

M. Lee, 2011 .

Probabilistic Risk Assessment of Station Blackouts in Nuclear Power Plants

Edoardo Patelli, Min Lee, Hindolo George-Williams, 2018, IEEE Transactions on Reliability.

Predicted Water Chemistry in the Primary Coolant Circuit of a Supercritical Water Reactor

T. Yeh, M. Lee, Hong-Ming Liu, 2013 .