Cihangir Celik Senior R&D Staff, Nuclear Criticality Safety Contact 865.576.1690 | CELIKC@ORNL.GOV All Publications Impact of recent ENDF nuclear data update, high initial enrichment and high burnup fuel on critical experiments applicability determination via the integral index ck for burnup credit validation Porosity in nuclear graphite and its impact on nuclear reactor science and criticality safety applications Final CRADA Report: NFE-23-09571 Criticality Safety Analysis for NuCycle Ratio of 1275 and 186-keV Gamma Ray Count Rates for Age Determination of Material in Uranium Hexafluoride Cylinders Perturbations to the 30B-10 Cylinder Criticality Control System Improving Transport Efficiency of HALEU Fuel with a Modified Criticality Control System in the 30B-10 NEUTRON FLUENCE AND KERMA RESPONSES TO BARE, STEEL-REFLECTED, AND LUCITE-REFLECTED STEADY-STATE OPERATIONS OF THE ORNL HEALTH PHYSICS RESEARCH REACTOR Benchmark Gap Assessment for the Manufacturing of High-Assay Low-Enriched Uranium Fuels SCALE Developments for the U.S. Nuclear Criticality Safety Program: Recent Achievements and Outlook Burnup Credit Loading Curves for High-Burnup and Extended Enrichment Fuels Bias and Bias Uncertainty for High Burnup and Extended Enrichment Fuels in Criticality Safety Analyses Validation Studies Towards an Energy Deposition Tally in SCALE/MAVRIC SCALE 6.3 Validation: Radiation Shielding ASSESSMENT OF VALIDATION FOR BURNUP CREDIT CALCULATIONS FOR LEU+ AND HIGH BURNUP FUEL Effect of Decay Time on Criticality Safety Analyses for High Burnup and Extended Enrichment Fuels Nuclear Data–Induced Uncertainties in Criticality Safety Analyses for High-Burnup and Extended Enrichment Fuels Photonuclear Physics in SCALE Using the Oak Ridge Subcritical Assembly for Gamma Ray Measurements IMPACT OF RECENT ENDF NUCLEAR DATA ON BURNUP CREDIT CRITICALITY SAFETY ANALYSES Overview of ORNL SCALE Shielding Analyses for Spent Nuclear Fuel Transportation and Storage Applications... SCALE 6.2.4 Validation: Radiation Shielding Update of the Nuclear Criticality Slide Rule Calculations: Plutonium systems – Delayed Fission Gamma Update of the Nuclear Criticality Slide Rule: Review of the Estimation of the Number of Fissions... Update of the Nuclear Criticality Slide Rule Calculations: Plutonium Systems – Delayed Fission Gamma SCALE Analysis of a Fluoride Salt-Cooled High-Temperature Reactor in Support of Severe Accident Analysis Pagination Current page 1 Page 2 Page 3 Next page ›› Last page Last » Key Links ORCID Organizations Fusion and Fission Energy and Science Directorate Nuclear Energy and Fuel Cycle Division Nuclear Applications, Methods, and Data Section Nuclear Code Systems and Methods Group SCALE
