פריטים דומים: OPENMC-BASED NEUTRONIC ANALYSIS OF METALLIC-FUELED ABR-1000 SODIUM-COOLED FAST REACTOR /
- NEUTRONIC PARAMETERS AND BURNUP ANALYSIS OF FRESH FUEL ASSEMBLIES OF WER-1000 KALININ-1 NPP USING THE DETERMINISTIC CODE DRAGONS /
- NEUTRONICS CHARACTERISTICS ANALYSIS OF ALFRED WITH LFR REFLECTOR COMPARISON AND CONCEPTUAL MPRR USING OPENMC /
- A STUDY ON CORE NEUTRONIC PARAMETERS OF THERMAL (BEAVRS PWR) AND FAST (NEA SFR) REACTORS USING MONTE CARLO CODES /
- NEUTRONIC ASSESSMENT AND THERMAL HYDRAULIC MODELING OF COATED FUEL CLADDING AND NANOFLUID COOLANTS IN A VVER-1200 REACTOR/
- COMPATIBILITY ANALYSIS OF STRUCTURAL MATERIALS USED IN REACTOR COOLANT PIPING SYSTEMS USING ANSYS AND OPENMCE /
- ANALYSIS OF NEUTRON IRRADIATION EMBRITTLEMENT OF VVER 1200 REACTOR PRESSURE VESSEL WALL /
נושא: Nuclear Science and Engineering.
- NUMERICAL INVESTIGATION OF TURBULENT NATURAL CONVECTION IN AN SFR CORE CATCHER /
- OPENMC-BASED NEUTRONIC ANALYSIS OF METALLIC-FUELED ABR-1000 SODIUM-COOLED FAST REACTOR /
- ASSESSMENT OF NATURAL RADIONUCLIDES AND HEAVY METALS IN SOIL SAMPLES OF JAMUNA RIVER BASIN, BANGLADESH /
- CONCEPTUAL DESIGN OF VVER-1200 SPENT NUCLEAR FUEL DRY STORAGE CASK : A NEUTRONIC, RADIATION SHIELDING AND THERMAL ANALYSIS /
- NEUTRONIC ASSESSMENT AND THERMAL HYDRAULIC MODELING OF COATED FUEL CLADDING AND NANOFLUID COOLANTS IN A VVER-1200 REACTOR/
- ENHANCING THE ACCIDENT TOLERANCE OF VVER-1200 FUEL ASSEMBLIES USING NANOPARTICLE-REINFORCED CLADDING: A COUPLED NEUTRONIC- THERMAL MULTIPHYSICS STUDY/
נושא: This Thesis Paper of NSE in BSc Program.
- NUMERICAL INVESTIGATION OF TURBULENT NATURAL CONVECTION IN AN SFR CORE CATCHER /
- OPENMC-BASED NEUTRONIC ANALYSIS OF METALLIC-FUELED ABR-1000 SODIUM-COOLED FAST REACTOR /
- ASSESSMENT OF NATURAL RADIONUCLIDES AND HEAVY METALS IN SOIL SAMPLES OF JAMUNA RIVER BASIN, BANGLADESH /
- CONCEPTUAL DESIGN OF VVER-1200 SPENT NUCLEAR FUEL DRY STORAGE CASK : A NEUTRONIC, RADIATION SHIELDING AND THERMAL ANALYSIS /
- NEUTRONIC ASSESSMENT AND THERMAL HYDRAULIC MODELING OF COATED FUEL CLADDING AND NANOFLUID COOLANTS IN A VVER-1200 REACTOR/
- ENHANCING THE ACCIDENT TOLERANCE OF VVER-1200 FUEL ASSEMBLIES USING NANOPARTICLE-REINFORCED CLADDING: A COUPLED NEUTRONIC- THERMAL MULTIPHYSICS STUDY/