787988 |
NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY |
Analysis and comparison of the 2D/1D and quasi-3D methods with the direct transport code SHARK |
2022-01-01 |
|
Chen Zhao, Xingjie Peng, Hongbo Zhang, Wenbo Zhao, Qing Li, Zhang Chen |
787987 |
NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY |
FTIR study of gamma and electron irradiated high-density polyethylene for high dose measurements |
2022-01-01 |
|
Hanan Al-Ghamdi, Khaled Farah, Aljawharah Almuqrin, Faouzi Hosni |
787986 |
NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY |
p Ignition and flame propagation in hydrogen-air layers from a geological nuclear waste repository: A preliminary study |
2022-01-01 |
10.1016/j.net.2021.07.011 |
Ryu, Je Ir, Woo, Seung Min, Lee, Manseok, Yoon, Hyun Chul |
787985 |
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 |
10.1016/j.net.2021.07.032 |
Bang, Jungjin, Choi, Gi Hyeon, Jerng, Dong-Wook, Bae, Sung-Won, Jang, Sunghyon, Ha, Sang Jun |
787984 |
NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY |
Analyses of hydrogen risk in containment filtered venting system using MELCOR |
2022-01-01 |
10.1016/j.net.2021.07.046 |
Choi, Gi Hyeon, Jerng, Dong-Wook, Kim, Tae Woon |
787983 |
NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY |
Analysis of pipe thickness reduction according to pH in FAC facility with In situ ultrasonic measurement real time monitoring |
2022-01-01 |
10.1016/j.net.2021.07.048 |
Oh, Se-Beom, Kim, Jongbeom, Lee, Jong-Yeon, Kim, Dong-Jin, Kim, Kyung-Mo |
787982 |
NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY |
Mechanical performance of additively manufactured austenitic 316L stainless steel |
2022-01-01 |
10.1016/j.net.2021.07.041 |
Kim, Kyu-Tae |
787981 |
NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY |
Numerical study on thermal-hydraulics of external reactor vessel cooling in high-power reactor using MARS-KS1.5 code: CFD-aided estimation of natural circulation flow rate |
2022-01-01 |
10.1016/j.net.2021.07.037 |
Song, Min Seop, Park, Il Woong, Kim, Eung Soo, Lee, Yeon-Gun |
787980 |
NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY |
Sensitivity analysis of input variables to establish fire damage thresholds for redundant electrical panels |
2022-01-01 |
10.1016/j.net.2021.07.044 |
Kim, Byeongjun, Lee, Jaiho, Shin, Weon Gyu |
787979 |
NUCLEAR ENGINEERING AND TECHNOLOGY : AN INTERNATIONAL JOURNAL OF THE KOREAN NUCLEAR SOCIETY |
How to incorporate human failure event recovery into minimal cut set generation stage for efficient probabilistic safety assessments of nuclear power plants |
2022-01-01 |
10.1016/j.net.2021.04.026 |
Jung, Woo Sik, Park, Seong Kyu, Weglian, John E., Riley, Jeff |