Comparison of applicability of current transition temperature shift models to SA533B-1 reactor pressure vessel steel of Korean nuclear reactors

by Ji-Hyun Yoon, Bong-Sang Lee
Published 2017-08-01

Machine learning modeling of irradiation embrittlement in low alloy steel of nuclear power plants

by Gyeong-Geun Lee, Min-Chul Kim, Bong-Sang Lee
Published 2021-12-01

EFFECTS OF TEMPERING AND PWHT ON MICROSTRUCTURES AND MECHANICAL PROPERTIES OF SA508 GR.4N STEEL

by KI-HYOUNG LEE, MYUNG JO JHUNG, MIN-CHUL KIM, BONG-SANG LEE
Published 2014-06-01

Fatigue crack growth characteristics of nitrogen-alloyed type 347 stainless steel under operating conditions of a pressurized water reactor

by Ki-Deuk Min, Seokmin Hong, Dae-Whan Kim, Bong-Sang Lee, Seon-Jin Kim
Published 2017-06-01

A practical power law creep modeling of alloy 690 SG tube materials

by Bong-Sang Lee, Jong-Min Kim, June-Yeop Kwon, Kwon-Jae Choi, Min-Chul Kim
Published 2021-09-01

Statistical analysis on the fluence factor of surveillance test data of Korean nuclear power plants

by Gyeong-Geun Lee, Min-Chul Kim, Ji-Hyun Yoon, Bong-Sang Lee, Sangyeob Lim, Junhyun Kwon
Published 2017-06-01