Jianwei Hu R&D Staff Member Contact huj1@ornl.gov All Publications Modeling Passive Fast-Neutron Emission Tomography of Spent Nuclear Fuel... Advancing the Fork detector for quantitative spent nuclear fuel verification Analysis of New Measurements of Isotopic Compositions in Spent Fuel Samples from Calvert Cliffs Unit 1 Reactor using SCALE 6.... Detection of Fuel Pin Diversion via Fast Neutron Emission Tomography... In-Field Performance Testing of the Fork Detector for Quantitative Spent Fuel Verification Analysis of new measurements of Calvert Cliffs spent fuel samples using SCALE 6.2 In-Field Performance Testing of the Fork Detector for Quantitative Spent Fuel Verification Phenomena Identification and Ranking Table (PIRT) for Fluoride High-Temperature Reactor (FHR) Neutronics... PWR and BWR spent fuel assembly gamma spectra measurements... High-Fidelity Modeling of Spent Fuel Assemblies for Advanced NDA Instrument Testings... Embedded Self-Shielding Method Applied to Doubly Heterogeneous Fully Ceramic Micro-Encapsulated Fuels... Re-evaluation of spent nuclear fuel assay data for the Three Mile Island unit 1 reactor and application to code validation U.S. Commercial Spent Nuclear Fuel Assembly Characteristics: 1968-2013 (NUREG/CR-7227) U. S. Commercial Spent Nuclear Fuel Assembly Characteristics: 1968 -2013 (NUREG/CR-7227) Re-evaluation of Spent Nuclear Fuel Assay Data for the Three Mile Island Unit 1 Reactor and Application to Code Validation... In-Field Performance Testing of the Fork Detector for Quantitative Spent Fuel Verification... Spent Fuel Modeling and Simulation Using ORIGAMI for Advanced NDA Instrument Testing... Impact of Nuclear Data Uncertainties on Calculated Spent Fuel Nuclide Inventories and Advanced NDA Instrument Response... Special Nuclear Material Inventory Processes at US Domestic Nuclear Power Plants... A New Approach to Fork Measurements Data Analysis by RADAR-CRISP and ORIGEN Integration Impact of Nuclear Data Uncertainties on Calculated Spent Fuel Nuclide Inventories and Advanced NDA Instrument Response Impact of Nuclear Data Uncertainties on Calculated Spent Fuel Nuclide Inventories and Advanced NDA Instrument Response Isotopic Impacts on the Performance of Self-Interrogation Neutron Resonance Densitometry for Spent Fuel Assay... Performance assessment of self-interrogation neutron resonance densitometry for spent nuclear fuel assay Pagination First page « First Previous page ‹‹ Page 1 Current page 2 Key Links Curriculum Vitae ORCID Organizations Fusion and Fission Energy and Science Directorate Nuclear Energy and Fuel Cycle Division Nuclear Modeling and Simulation Development and Deployment Section Research and Test Reactor Physics Group SCALE