Jianwei Hu R&D Staff Member Contact huj1@ornl.gov All Publications Advancing the Fork detector for quantitative spent nuclear fuel verification... Modeling and Simulation of Fuel Burnup in Pebble Bed Reactors Volume 6: Experiment Facility Spectrum Tailoring Assessment of Core Physics Characteristics of Extended Enrichment and Higher Burnup LWR Fuels using the Polaris/PARCS Two-Ste... CTF: A modernized, production-level, thermal hydraulic solver for the solution of industry-relevant challenge problems in pre... Metallic Fuel Performance Benchmarks for Versatile Test Reactor Applications... Development of a Fast-Spectrum Self-Powered Neutron Detector for Molten Salt Experiments in the Versatile Test Reactor... Development of a U-19Pu-10Zr fuel performance benchmark case based on the IFR-1 experiment... Analysis of PNAR Spent Fuel Safeguards Measurements using the ORIGEN Data Analysis Module... FORK EXPERIMENTS IN THE HOT CELL USING SPENT FUEL RODS FOR INTERNATIONAL NUCLEAR SAFEGUARDS... Analysis with the ORIGEN Module of PNAR Spent Fuel Measurements for Nuclear Safeguards Applications... Improvement of CTF for RIA Analysis... CTF Theory Manual... CTF User's Manual... Sensitivity and Uncertainty Analysis of Core Criticality for the Transformational Challenge Reactor... A Metallic Fuel Performance Benchmark Problem Based on the IFR-1 Experiment... Validation of ORIGEN for VVER-440 Spent Fuel with Application to Fork Detector Safeguards Measurements... CTF 4.0 User's Manual... CTF 4.0 Theory Manual... 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 tomogra... 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.... Pagination Current page 1 Page 2 Next page ›› Last page Last » 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
