T. Nakajima

FEMAXI-IV: A computer code for the analysis of thermal and mechanical behavior of light water reactor fuel rods

T. Nakajima, H. Saito, T. Osaka, 1994 .

Physical model features and validation status of three-dimensional simulation model for BWR in-vessel core degradation

T. Nakajima, T. Okawa, S. Shiba, 2017 .

Modeling and verification of three-dimensional simulation for BWR in-vessel core degradation

T. Nakajima, T. Okawa, 2017 .