| 1 |
S.-H. Park, W.-J. Jung, T.-H. Kim, S.-Y. Tom Lee, Can renewable energy replace nuclear power in Korea? An economic valuation analysis, Nucl. Eng. Technol. 48 (2016) 559-571./
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| 2 |
H.-G. Kim, J.-H. Yang, W.-J. Kim, Y.-H. Koo, Development status of accident-tolerant fuel for light water reactors in Korea, Nucl. Eng. Technol. 48 (2016) 1-15./
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| 3 |
T. Miura, H. Matsue, Precise determination of silicon in ceramic reference materials by prompt gamma activation analysis at JRR-3, Nucl. Eng. Technol. 48 (2016) 299-303./
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| 4 |
J.B. Kim, J.Y. Jeong, T.H. Lee, S.K. Kim, D.J. Euh, H.K. Joo, On the safety and performance demonstration tests of prototype Gen-IV sodium-cooled fast reactor and validation and verification of computational codes, Nucl. Eng. Technol. 48 (2016) 1083-1095./
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| 5 |
J.W. Yoo, J.W. Chang, J.Y. Lim, J.S. Cheon, T.H. Lee, S.K. Kim, K.L. Lee, H.K. Joo, Overall system description and safety characteristics of prototype Gen IV sodium cooled fast reactor in Korea, Nucl. Eng. Technol. 48 (2016) 1059-1070./
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| 6 |
S.-H. Park, W.-J. Jung, T.-H. Kim, S.-Y. Tom Lee, Can Renewable Energy Replace Nuclear Power in Korea? An Economic Valuation Analysis, Nucl. Eng. Technol. 48 (2) (2016) 559-571./
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| 7 |
R. Gharari, N. Poursalehi, M.R. Abbasi, M. Aghaie, Implementation of strength pareto evolutionary algorithm (SPEA-II) in the multi-objective burnable poison placement optimization of KWU PWR, Nucl. Eng. Technol. (2016), http://dx.doi.org/10.1016/j.net.2016.04.004./
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| 8 |
S.H. Park, W.J. Jung, T.H. Kim, S.Y. Tom Lee, Can renewable energy replace nuclear power in Korea? An economic valuation analysis, Nucl. Eng. Technol. 48 (2016) 559-571./
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| 9 |
W. Wang, S. Liu, G. Xu, B. Zhang, Q. Huang, Effect of thermal aging on microstructure and mechanical properties of China low-activation martensitic steel at $550^{\circ}C$, Nucl. Eng. Technol. 48 (2016) 518-524./
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| 10 |
T.K. Kim, S. Noh, S.H. Kang, J.J. Park, H.J. Jin, M.K. Lee, J. Jang, C.K. Rhee, Current status and future prospective of advanced radiation resistant oxide dispersion strengthened steel (ARROS) development for nuclear reactor system applications, Nucl. Eng. Technol. 48 (2016) 572-594./
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