| 787998 |
NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY |
Fractional Radioactive Decay Law and Bateman equations |
2022-01-01 |
|
C.-A. Cruz-Lopez, G. Espinosa-Paredes |
| 787997 |
NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY |
Development of mechanistic cladding rupture model for severe accident analysis and application in PHEBUS FPT3 experiment |
2022-01-01 |
|
Pengcheng Gao, Bin Zhang, Jishen Li, Jianqiang Shan |
| 787996 |
NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY |
Seismic Performance Assessment of NPP Concrete Containments Considering Recent Ground Motions in South Korea |
2022-01-01 |
|
김찬영, Eun Jeong Cha, 신명수 |
| 787995 |
NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY |
Possibility of Curium as a Fuel for VVER-1200 Reactor |
2022-01-01 |
|
Afroza Shelley, Mahmud Hasan Ovi |
| 787994 |
NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY |
Study on gamma radiation attenuation and non-ionizing shielding effectiveness of Niobium-reinforced novel polymer composite |
2022-01-01 |
|
Ferdi. Akman, H. Ogul, I. Ozkan, M.R. Kaçal, O. Agar, H. Polat, K. Dilsiz |
| 787993 |
NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY |
Analytical Method to Estimate Cross-Section Stress Profiles for Reactor Vessel Nozzle Corners under Internal Pressure |
2022-01-01 |
|
오창식, 이상민, 정명조 |
| 787992 |
NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY |
MECHANICAL PERFORMANCE OF ADDITIVELY MANUFACTURED AUSTENITIC 316L STAINLESS STEEL |
2022-01-01 |
|
김규태 |
| 787991 |
NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY |
CFD/RELAP5 Coupling Analysis of the ISP No. 43 Boron Dilution Experiment |
2022-01-01 |
|
Linrong Ye, Hao Yu, Mingjun Wang, Qianglong Wang, Wenxi Tian, Suizheng Qiu, G.H. Su |
| 787990 |
NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY |
Analysis of Steam Generator Tube Rupture Accidents for the Development of Mitigation Strategies |
2022-01-01 |
|
방정진, 최기현, 정동욱, 배성원, Sunghyon Jang, 하상준 |
| 787989 |
NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY |
Radioactive gas diffusion simulation and inhaled effective dose evaluation during nuclear decommissioning |
2022-01-01 |
|
Li-qun Yang, Yong-kuo Liu, Min-jun Peng, Abiodun Ayodeji, Zhi-tao Chen, Ze-yu Long |
