Cihangir Celik Senior R&D Staff, Nuclear Criticality Safety Contact CELIKC@ORNL.GOV All Publications The MAVRIC-Shift Sequence in SCALE for Radiation Transport and Shielding Calculations with Automated Variance Reduction and Parallel Computing Monte Carlo Uncertainty Quantification in UF6 Cylinder Neutron Emissions... A Directional Detector Response Function for Anisotropic Detectors Assessment of SCALE Capabilities for High Temperature Reactor Modeling and Simulation... Update of the Nuclear Criticality Slide Rule Calculations - Studies with Common Shielding Materials Evaluation of the Concrete Shield Compositions from the 2010 Criticality Accident Alarm System Benchmark Experiments at the CEA Valduc SILENE Facility Analysis Capability and Data Needs Identified During the Evaluation of the SILENE CAAS Benchmarks NCSP FY 2015 AMPX Annual Report Creation of problem-dependent Doppler-broadened cross sections in the KENO Monte Carlo code Creation of problem-dependent Doppler-broadened cross sections in the KENO Monte Carlo code Neutron Activation Foil and Thermoluminescent Dosimeter Responses to a Polyethylene Reflected Pulse of the CEA Valduc SILENE Critical Assembly (ORNL/TM-2016/317) Neutron Activation and Thermoluminescent Detector Responses to a Bare Pulse of the CEA Valduc SILENE Critical Assembly (ORNL/TM-2015/462) Neutron Activation Foil and Thermoluminescent Dosimeter Responses to a Lead Reflected Pulse of the CEA Valduc SILENE Critical Assembly (ORNL/TM-2016/316) CRITICALITY SAFETY ENHANCEMENTS FOR SCALE 6.2 AND BEYOND EVALUATION OF THE CONCRETE SHIELD COMPOSITIONS FROM THE 2010 CRITICALITY ACCIDENT ALARM SYSTEM BENCHMARK EXPERIMENTS AT THE C... AMPX: A Modern Cross Section Processing System for Generating Nuclear Data Libraries Monte Carlo Capabilities of the SCALE Code System... ADVANCEMENTS IN MONTE CARLO CAPABILITIES FOR SCALE 6.2 Monte Carlo Capabilities of the SCALE Code System Enhancements in Continuous-Energy Monte Carlo Capabilities for SCALE 6.2... PROBLEM DEPENDENT DOPPLER BROADENING OF CONTINUOUS ENERGY CROSS SECTIONS IN THE KENO MONTE CARLO COMPUTER CODE... Simulation of Watts Bar Unit 1 Initial Startup Tests with Continuous Energy Monte Carlo Methods Monte Carlo Capabilities of the SCALE Code System... Validation of Criticality Safety Calculations with SCALE 6.2... Hybrid Technique in SCALE for Fission Source Convergence Applied to Used Nuclear Fuel Analysis... Pagination First page « First Previous page ‹â¶Ä¹ Page 1 Current page 2 Page 3 Next page ›â¶Äº Last page Last » Key Links Organizations Fusion and Fission Energy and Science Directorate Nuclear Energy and Fuel Cycle Division Nuclear Data, Criticality Safety, and Radiation Transport Section Nuclear Criticality Safety Group SCALE
