| 1 |
B. Ebiwonjumi, et al., Uncertainty quantification of PWR spent fuel due to nuclear data and modeling parameters, Nuclear Engineering and Technology 53 (2021) 715-731./
|
|
| 2 |
B. Ebiwonjumi, C. Kong, P. Zhang, A. Cherezov, D. Lee, Uncertainty quantification of PWR spent fuel due to nuclear data and modelling parameters, Nucl. Eng. Technol. (2021), https://doi.org/10.1016/j.net.2020.07.012./
|
|
| 3 |
J. Jang, B. Ebiwonjumi, W. Kim, A. Cherezov, J. Park, D. Lee, Validation of Isotope Inventory Prediction for Back-End Cycle Management by Two-step Method, 2021, https://doi.org/10.1016/j.net.2021.01.009./
|
|
| 4 |
J. Jang, B. Ebiwonjumi, W. Kim, J. Park, J. Choe, D. Lee, Validation of spent nuclear fuel decay heat calculation by a two-step method, Nucl. Eng. Technol. (2021), https://doi.org/10.1016/j.net.2020.06.028./
|
|
| 5 |
T.Y. Kong, et al., Administrative dose control for occupationally-exposed workers in Korean nuclear power plants, Nuclear Engineering and Technology 53 (1) (2021) 351-356./
|
|
| 6 |
Y. Kim, J. Kim, J. Park, S.Y. Choi, S. Kim, W. Jung, H.E. Kim, S.K. Shin, An algorithm for evaluating time-related human reliability using instrumentation cues and procedure cues, Nucl. Eng. Technol. 53 (2) (2021) 368-375./
|
|
| 7 |
Y.A. Suh, J. Kim, S.Y. Park, Time uncertainty analysis method for level 2 human reliability analysis of severe accident management strategies, Nucl. Eng. Technol. 53 (2) (2021) 484-497./
|
|
| 8 |
Y. Kirimoto, Y. Hirotsu, K. Nonose, K. Sasou, Development of a human reliability analysis (HRA) guide for qualitative analysis with emphasis on narratives and models for tasks in extreme conditions, Nucl. Eng. Technol. 53 (2) (2021) 376-385./
|
|
| 9 |
J. Byun, W.N. Choi, H.R. Kim, Radiological safety assessment of lead shielded spent resin treatment facility with the treatment capacity of 1 ton/day, Nucl. Eng. Technol. 53 (2021) 273-281./
|
|
| 10 |
Minho Kim, Bong Hwan Hong, Ilsung Cho, Chawon Park, Sun-Hong Min, Won Taek Hwang, Wonho Lee, Kyeong Min Kim, Design of a scintillator-based prompt gamma camera for boron-neutron capture therapy: comparison of SrI2 and GAGG using Monte-Carlo simulation, Nuclear Engineering and Technology 53/2 (2021) 626-636, https://doi.org/10.1016/j.net.2020.07.010./
|
|