| Adsorption and degradation of sulfadiazine over nanoscale zero-valent iron encapsulated in three-dimensional graphene network through oxygen-driven heterogeneous Fenton-like … Y Yang, L Xu, W Li, W Fan, S Song, J Yang Applied Catalysis B: Environmental 259, 118057, 2019 | 128 | 2019 |
| Three-dimensional macroporous graphene-wrapped zero-valent copper nanoparticles as efficient micro-electrolysis-promoted Fenton-like catalysts for metronidazole removal L Xu, Y Yang, W Li, Y Tao, Z Sui, S Song, J Yang Science of The Total Environment 658, 219-233, 2019 | 82 | 2019 |
| Dissolution and degradation of nuclear grade cationic exchange resin by Fenton oxidation combining experimental results and DFT calculations L Xu, X Meng, M Li, W Li, Z Sui, J Wang, J Yang Chemical Engineering Journal 361, 1511-1523, 2019 | 41 | 2019 |
| A Statistical Model and DFT Study of the Fragmentation Mechanisms of Metronidazole by Advanced Oxidation Processes L Xu, W Li, P Désesquelles, NT Van-Oanh, S Thomas, J Yang The Journal of Physical Chemistry A 123 (4), 933-942, 2019 | 34 | 2019 |
| Best Estimate Plus Uncertainty analysis of a large break LOCA on Generation III reactor with RELAP5 J Yang, Y Yang, C Deng, M Ishii Annals of Nuclear Energy 127, 326-340, 2019 | 28 | 2019 |
| Research on scaling design and applicability evaluation of integral thermal-hydraulic test facilities: A review C Deng, X Zhang, Y Yang, J Yang Annals of Nuclear Energy 131, 273-290, 2019 | 26 | 2019 |
| Overview of filtered containment venting system in Nuclear Power Plants in Asia J Yang, DY Lee, S Miwa, S Chen Annals of Nuclear Energy 119, 87-97, 2018 | 25 | 2018 |
| Best-estimate calculation plus uncertainty analysis of SBLOCA transient for the scale-down passive test facility C Deng, L Chen, J Yang, Q Wu Progress in Nuclear Energy 112, 191-201, 2019 | 19 | 2019 |
| Assessment of passive safety system performance under main steam line break accident J Lim, SW Choi, J Yang, DY Lee, S Rassame, T Hibiki, M Ishii Annals of Nuclear Energy 64, 287-294, 2014 | 19 | 2014 |
| Assessment of performance of BWR passive safety systems in a small break LOCA with integral testing and code simulation J Yang, SW Choi, J Lim, DY Lee, S Rassame, T Hibiki, M Ishii Nuclear Engineering and Design 247, 128-135, 2012 | 19 | 2012 |
| Assessment of passive safety system performance under gravity driven cooling system drain line break accident J Lim, J Yang, SW Choi, DY Lee, S Rassame, T Hibiki, M Ishii Progress in Nuclear Energy 74, 136-142, 2014 | 18 | 2014 |
| Counterpart experimental study of ISP-42 PANDA tests on PUMA facility J Yang, SW Choi, J Lim, DY Lee, S Rassame, T Hibiki, M Ishii Nuclear Engineering and Design 258, 249-257, 2013 | 15 | 2013 |
| Critical heat flux in TRIGA-fueled reactors cooled by natural convection M Avery, J Yang, M Anderson, M Corradini, E Feldman, F Dunn, J Matos Nuclear science and engineering 172 (3), 249-258, 2012 | 15 | 2012 |
| Enhanced heterogeneous Fenton-like degradation of nuclear-grade cationic exchange resin by nanoscale zero-valent iron: experiments and DFT calculations L Xu, P Sun, X Meng, H Shen, W Li, J Wang, J Yang Environmental Science and Pollution Research 27 (12), 13773-13789, 2020 | 12 | 2020 |
| Overview of the experimental studies and numerical simulations on the filtered containment venting systems with wet scrubbers S Dong, J Yang Annals of Nuclear Energy 132, 461-485, 2019 | 11 | 2019 |
| Experimental investigation of void distribution in Suppression Pool during the initial blowdown period of a Loss of Coolant Accident using air–water two-phase mixture S Rassame, M Griffiths, J Yang, DY Lee, P Ju, SW Choi, T Hibiki, M Ishii Annals of Nuclear Energy 73, 53-67, 2014 | 11 | 2014 |
| Best estimate plus uncertainty analysis of a small‐break LOCA on an advanced Generation‐III pressurized water reactor Y Yang, C Deng, J Yang International Journal of Energy Research 45 (8), 11916-11929, 2021 | 8 | 2021 |
| Simulation and uncertainty analysis of main steam line break accident on an integral test facility Y Yang, J Yang, C Deng, M Ishii Annals of Nuclear Energy 144, 107565, 2020 | 8 | 2020 |
| Numerical investigation of the thermal-hydraulic characteristics of AP1000 steam generator U-tubes ZG Sui, J Yang, XY Zhang, Y Yao International Journal of Advanced Nuclear Reactor Design and Technology 2, 52-59, 2020 | 7 | 2020 |
| Behaviors of passive safety systems under a Feed Water Line Break LOCA on a Generation III+ Boiling Water Reactor Jun Yang, Jaehyok Lim, Sung Won Choi, Doo Yong Lee, Somboon Rassame, Takashi ... Progress in Nuclear Energy 83, 35-42, 2015 | 7 | 2015 |
Mamoru IshiiDistinguished Professor of Nuclear Engineering in Purdue UniversityVerified email at purdue.edu
