Hao Jiang R&D Mechanical Engineer Contact 865.574.5712 | JIANGH@ORNL.GOV All Publications HYDROGEN VESSEL WELD POROSITY STRESS ANALYSIS USING CT SCAN DATA REPEATABILITY AND UNCERTAINTY STUDY OF STRAIN MEASURED ON COUPLED FLUID-STRUCTURE VESSELS IN RESPONSE TO HIGH INTENSITY PROTON PULSES Implementing bubbly mercury material model (R-P model) in the pulse simulation to predict strain on the Spallation Neutron So... Small-bubble gas injection to mitigate cavitation-induced erosion damage and reduce strain in target vessels at the Spallation Neutron Source Model calibration of the liquid mercury spallation target using evolutionary neural networks and sparse polynomial expansions Bifurcation Buckling Analysis and Non-Linear Collapse Analysis of Teardrop Shaped Vacuum Chamber Bayesian inverse uncertainty quantification of the physical model parameters for the spallation neutron source first target station Quantifying the reduction in cavitation-induced erosion damage in the Spallation Neutron Source mercury target by means of small-bubble gas injection Design and Structural Assessment of the Spallation Neutron Source 2.0 MW Target Fatigue analysis of the Spallation Neutron Source 2 MW target design Development of cone-wedge-ring-expansion test to evaluate the tensile HOOP properties of nuclear fuel cladding High burn-up spent nuclear fuel transport reliability investigation High burn-up spent nuclear fuel transport reliability investigation EXPANDING PLUG WEDGE TEST FOR EVALUATING HOOP TENSILE PROPERTIES OF FUEL CLADDING FATIGUE BEHAVIOR OF SPENT NUCLEAR FUEL RODS IN SIMULATED TRANSPORTATION ENVIRONMENT Spent Nuclear Fuel Dynamic Performance under Normal Condition of Transport Spent Nuclear Fuel Transport Reliability Study Spent Nuclear Fuel System Dynamic Stability under Normal Conditions of Transportion... The impact of interface bonding efficiency on high-burnup spent nuclear fuel dynamic performance ... High-Burnup Spent Nuclear Fuel Interface Bonding Efficiency Study Grid-to-rod flow-induced impact study for PWR fuel in reactor Spent Nuclear Fuel Vibration Integrity Study... LESSONS LEARNED FROM CIRFT TESTING ON SNF VIBRATION INTEGRITY STUDY... High Burn-Up Spent Nuclear Fuel Vibration Integrity Study – 15134... An Innovative Testing Protocol to Study Spent Nuclear Fuel Vibration Integrity under Normal Condition of Transportation Pagination Current page 1 Page 2 Next page ›â¶Äº Last page Last » Key Links Curriculum Vitae Organizations Neutron Technologies Division Neutron Technologies Engineering Section Source Development and Engineering Group
