| 745968 |
NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY |
Design of muon production target system for the RAON μSR facility in Korea |
2021-09-25 |
10.1016/j.net.2021.03.023 |
Jeong, Jae Young, Kim, Jae Chang, Kim, Yonghyun, Pak, Kihong, Kim, Kyungmin, Park, Junesic, Son, Jaebum, Kim, Yong Kyun, Lee, Wonjun, Lee, Ju Hahn |
| 745967 |
NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY |
Use of Monte Carlo code MCS for multigroup cross section generation for fast reactor analysis |
2021-09-25 |
10.1016/j.net.2021.03.005 |
Nguyen, Tung Dong Cao, Lee, Hyunsuk, Lee, Deokjung |
| 745966 |
NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY |
Uncertainty quantification in decay heat calculation of spent nuclear fuel by STREAM/RAST-K |
2021-09-25 |
10.1016/j.net.2021.03.010 |
Jang, Jaerim, Kong, Chidong, Ebiwonjumi, Bamidele, Cherezov, Alexey, Jo, Yunki, Lee, Deokjung |
| 745965 |
NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY |
Analysis of severe accident progression and Cs behavior for SBO event during mid-loop operation of OPR1000 using MELCOR |
2021-09-25 |
10.1016/j.net.2021.03.006 |
Park, Yerim, Shin, Hoyoung, Kim, Seungwoo, Jin, Youngho, Kim, Dong Ha, Jae, Moosung |
| 745964 |
NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY |
Effect analysis of ISLOCA pathways on fission product release at Westinghouse 2-loop PWR using MELCOR |
2021-09-25 |
10.1016/j.net.2021.03.020 |
Kim, Seungwoo, Park, Yerim, Jin, Youngho, Kim, Dong Ha, Jae, Moosung |
| 745963 |
NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY |
A practical power law creep modeling of alloy 690 SG tube materials |
2021-09-25 |
10.1016/j.net.2021.03.004 |
Lee, Bong-Sang, Kim, Jong-Min, Kwon, June-Yeop, Choi, Kwon-Jae, Kim, Min-Chul |
| 745962 |
NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY |
Studies on the effect of thermal shock on crack resistance of 20MnMoNi55 steel using compact tension specimens |
2021-09-25 |
10.1016/j.net.2021.03.029 |
Thamaraiselvi, K., Vishnuvardhan, S. |
| 745961 |
NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY |
3D reconstruction of two-phase random heterogeneous material from 2D sections: An approach via genetic algorithms |
2021-09-25 |
10.1016/j.net.2021.03.012 |
Pizzocri, D., Genoni, R., Antonello, F., Barani, T., Cappia, F. |
| 745960 |
NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY |
Corrosion fatigue crack growth behavior of 316LN stainless steel in high-temperature pressurized water |
2021-09-25 |
10.1016/j.net.2021.03.016 |
Zhang, Ziyu, Tan, Jibo, Wu, Xinqiang, Han, En-Hou, Ke, Wei |
| 745959 |
NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY |
Experimental investigation of zinc sodium borate glass systems containing barium oxide for gamma radiation shielding applications |
2021-09-25 |
10.1016/j.net.2021.04.002 |
Aboalatta, A., Asad, J., Humaid, M., Musleh, H., Shaat, S.K.K., Ramadan, Kh, Sayyed, M.I., Alajerami, Y., Aldahoudi, N. |
