Jianwei Hu R&D Staff Member Contact HUJ1@ORNL.GOV All Publications Molten Salt Reactors and Associated Safeguards Challenges and Opportunities DEVELOPMENT OF A NUCLEAR FUEL SAFEGUARDS VERIFICATION TECHNOLOGY FOR NEW FACILITY TYPES: Use of fast neutron emission tomography for spent fuel verification A Design Study of the Parallel-Slit Ring Collimator for Fast Neutron Emission Tomography of Spent Fuel 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 6.2 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 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 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... 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 A New Approach to Fork Measurements Data Analysis by RADAR-CRISP and ORIGEN Integration Pagination First page « First Previous page ‹â¶Ä¹ Page 1 Current page 2 Page 3 Next page ›â¶Äº Last page Last » Key Links Curriculum Vitae 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
