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No Journal_name Subject Date DOI Author
732368 NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY Research on rapid source term estimation in nuclear accident emergency decision for pressurized water reactor based on Bayesian network 2021-08-25 10.1016/j.net.2021.02.028 Wu, Guohua, Tong, Jiejuan, Zhang, Liguo, Yuan, Diping, Xiao, Yiqing
732367 NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY Leak flow prediction during loss of coolant accidents using deep fuzzy neural networks 2021-08-25 10.1016/j.net.2021.01.040 Park, Ji Hun, An, Ye Ji, Yoo, Kwae Hwan, Na, Man Gyun
732366 NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY Control of a pressurized light-water nuclear reactor two-point kinetics model with the performance index-oriented PSO 2021-08-25 10.1016/j.net.2021.02.018 Mousakazemi, Seyed Mohammad Hossein
732365 NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY HCCR breeding blankets optimization by changing neutronic constrictions 2021-08-25 10.1016/j.net.2021.02.016 Zadfathollah Seighalani, R., Sedaghatizade, M., Sadeghi, H.
732364 NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY Hydrogen isotope exchange behavior of protonated lithium metal compounds 2021-08-25 10.1016/j.net.2021.02.013 Park, Chan Woo, Kim, Sung-Wook, Sihn, Youngho, Yang, Hee-Man, Kim, Ilgook, Lee, Kwang Se, Roh, Changhyun, Yoon, In-Ho
732363 NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY Evaluating thermal stability of rare-earth containing wasteforms at extraordinary nuclear disposal conditions 2021-08-25 10.1016/j.net.2021.02.025 Kim, Miae, Hong, Kyong-Soo, Lee, Jaeyoung, Byeon, Mirang, Jeong, Yesul, Kim, Jong Hwa, Um, Wooyong, Kim, Hyun Gyu
732362 NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY Effect of mechanical alloying on the microstructural evolution of a ferritic ODS steel with (Y-Ti-Al-Zr) addition processed by Spark Plasma Sintering (SPS) 2021-08-25 10.1016/j.net.2021.02.002 Macia, E., Garcia-Junceda, A., Serrano, M., Hong, S.J., Campos, M.
732361 NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY Effect of thermal aging on the mechanical, intergranular corrosion and corrosion fatigue properties of Z3CN20.09M cast duplex stainless steel 2021-08-25 10.1016/j.net.2021.02.001 Ti, Wenxin, Wu, Huanchun, Xue, Fei, Zhang, Guodong, Peng, Qunjia, Fang, Kewei, Wang, Xitao
732360 NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY Environmental fatigue correction factor model for domestic nuclear-grade low-alloy steel 2021-08-25 10.1016/j.net.2021.02.014 Gao, Jun, Liu, Chang, Tan, Jibo, Zhang, Ziyu, Wu, Xinqiang, Han, En-Hou, Shen, Rui, Wang, Bingxi, Ke, Wei
732359 NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY A study of predicting irradiation-induced transition temperature shift for RPV steels with XGBoost modeling 2021-08-25 10.1016/j.net.2021.02.015 Xu, Chaoliang, Liu, Xiangbing, Wang, Hongke, Li, Yuanfei, Jia, Wenqing, Qian, Wangjie, Quan, Qiwei, Zhang, Huajian, Xue, Fei