مواد مشابهة: THERMAL HYDRAULICS ANALYSIS IN TRIANGULAR SUB-CHANNEL FOR 3MW TRIGA MARK II RESEARCH REACTOR BY USING ANSYS SOFTWARE /
- ANALYSIS OF NEUTRONICS SAFETY PRAMETERS AND CORE BURNUP LIFETIME OF BAEC TRIGA MARK-II RESEARCH REACTOR USING THE DETERMINISTIC TRIGAP AND TRIGLAV CODES /
- A STUDY FOR OBTAINING A BETTER CORE CONFIGURATION OF THE TRIGA MARK-II RESEARCH RECTOR AT AERE
- ANALYSIS OF STRUCTURAL SAFETY PARAMETERS AND THERMAL BEHAVIOR OF THE FUEL ASSEMBLY OF A GENERIC VVER-1200 NUCLEAR REACTOR USING ANSYS /
- ANALYSIS OF NEUTRONICS SAFETY PARAMETERS AND CORE BURNUP LIFETIME OF BAEC TRIGA MARK-II RESEARCH REACTOR USING THE DETERMINISTIC TRIGAP AND TRIGLAV CODES
- COMPATIBILITY ANALYSIS OF STRUCTURAL MATERIALS USED IN REACTOR COOLANT PIPING SYSTEMS USING ANSYS AND OPENMCE /
- REACTOR THERMAL HYDRAULICS ANALYSIS OF NUSCALE SUBCHANNEL USING ALUMINA NANOFLUID /
موضوع: Nuclear Science and Engineering.
- REACTOR THERMAL HYDRAULICS ANALYSIS OF NUSCALE SUBCHANNEL USING ALUMINA NANOFLUID /
- 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/
موضوع: This Thesis Paper of NSE in B.Sc Program.
- ANALYSIS OF RADIATION DOSE ENHANCEMENT IN BRACHYTHERAPY IN PRESENCE OF GOLD (AU), SILVER (AG) AND GADOLINIUM (GD) NANOPARTICLES USING OPENMC /
- THERMAL HYDRAULICS ANALYSIS IN TRIANGULAR SUB-CHANNEL FOR 3MW TRIGA MARK II RESEARCH REACTOR BY USING ANSYS SOFTWARE /
- FREQUENCY CONTROL OF NUCLEAR-RENEWABLE HYBRID ENERGY SYSTEMS USING OPTIMAL PID AND FOPID CONTROLLERS /