| Grid-to-rod flow-induced impact study for PWR fuel in reactor H Jiang, J Qu, RY Lu, JAJ Wang Progress in Nuclear Energy 91, 355-361, 2016 | 44 | 2016 |
| Development of U-frame bending system for studying the vibration integrity of spent nuclear fuel H Wang, JAJ Wang, T Tan, H Jiang, TS Cox, RL Howard, BB Bevard, ... Journal of Nuclear Materials 440 (1-3), 201-213, 2013 | 39 | 2013 |
| Progress Letter Report on U Frame Test Setup and Bending Fatigue Test for Vibration Integrity Study (Out-of-Cell Fatigue Testing Development–Task 2.2) JAJ Wang, H Wang, T Tan, H Jiang, T Cox, Y Yan ORNL/TM-2011/531, Oak Ridge National Laboratory, Oak Ridge, TN, 2012 | 34 | 2012 |
| Methodology for mechanical property testing of fuel cladding using an expanding plug wedge test H Jiang, JAJ Wang Journal of nuclear materials 446 (1-3), 27-37, 2014 | 26 | 2014 |
| Spent nuclear fuel system dynamic stability under normal conditions of transportation H Jiang, JAJ Wang Nuclear Engineering and Design 310, 1-14, 2016 | 25 | 2016 |
| High burn-up spent nuclear fuel transport reliability investigation JA Wang, H Wang, H Jiang, B Bevard Nuclear Engineering and Design 330, 497-515, 2018 | 22 | 2018 |
| FY14 Status Report: CIRFT Testing Results on High Burnup UNF JAJ Wang, H Wang, H Jiang Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States). High …, 2014 | 14 | 2014 |
| Development of cone-wedge-ring-expansion test to evaluate the tensile hoop properties of nuclear fuel cladding H Jiang, JAJ Wang Progress in Nuclear Energy 108, 372-380, 2018 | 13 | 2018 |
| The impact of interface bonding efficiency on high-burnup spent nuclear fuel dynamic performance H Jiang, JAJ Wang, H Wang Nuclear Engineering and Design 309, 40-52, 2016 | 13 | 2016 |
| Small-bubble gas injection to mitigate cavitation-induced erosion damage and reduce strain in target vessels at the Spallation Neutron Source David A.McClintock, YunLiu, Douglas R.Bruce, Drew E.Winder, Richard G ... Materials & Design 221 (110937), 2022 | 11 | 2022 |
| Bayesian inverse uncertainty quantification of the physical model parameters for the spallation neutron source first target station MI Radaideh, L Lin, H Jiang, S Cousineau Results in Physics 36, 105414, 2022 | 11 | 2022 |
| Model calibration of the liquid mercury spallation target using evolutionary neural networks and sparse polynomial expansions MI Radaideh, H Tran, L Lin, H Jiang, D Winder, S Gorti, G Zhang, J Mach, ... Nuclear Instruments and Methods in Physics Research Section B: Beam …, 2022 | 10 | 2022 |
| Quantifying the reduction in cavitation-induced erosion damage in the Spallation Neutron Source mercury target by means of small-bubble gas injection H Jiang, D Winder, D McClintock, D Bruce, R Schwartz, M Kyte, T Carroll Wear 496, 204289, 2022 | 10 | 2022 |
| Fatigue analysis of the Spallation Neutron Source 2 MW target design J Mach, K Johns, S Gorti, H Jiang Nuclear Instruments and Methods in Physics Research Section A: Accelerators …, 2021 | 10 | 2021 |
| Material damage modeling and detection in a homogeneous thin metallic sheet and sandwich panel using passive acoustic transmission H Jiang, DE Adams, K Jata Structural Health Monitoring 5 (4), 373-387, 2006 | 8 | 2006 |
| Design and structural assessment of the Spallation Neutron Source 2.0 MW target K Johns, J Mach, S Gorti, H Jiang Nuclear Instruments and Methods in Physics Research Section A: Accelerators …, 2021 | 7 | 2021 |
| FY 2016 Status Report: Documentation of All CIRFT Data including Hydride Reorientation Tests JA Wang, H Wang, H Jiang, Y Yan, BB Bevard, JM Scaglione ORNL/SR-2016/424, DOE M2FT-16OR080202031, Oak Ridge, TN: Oak Ridge National …, 2016 | 7 | 2016 |
| CIRFT testing of high-burnup used nuclear fuel rods from pressurized water reactor and boiling water reactor environments JAJ Wang, H Wang, H Jiang, Y Yan Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States), 2015 | 6 | 2015 |
| Development of cone wedge ring expansion test to evaluate mechanical properties of clad tubing structure JAJ Wang Oak Ridge National Lab.(ORNL), Oak Ridge, TN (United States). High …, 2016 | 5 | 2016 |
| Potential Impact of Interfacial Bonding Efficiency on Used Nuclear Fuel Vibration Integrity During Normal Transportation H Jiang, JAJ Wang, H Wang Pressure Vessels and Piping Conference 46032, V06AT06A021, 2014 | 5 | 2014 |
Jy-An WangOak Ridge National Laboratory在 ornl.gov 的电子邮件经过验证
