Podobné jednotky: NEUTRONIC PARAMETERS AND BURNUP ANALYSIS OF FRESH FUEL ASSEMBLIES OF WER-1000 KALININ-1 NPP USING THE DETERMINISTIC CODE DRAGONS /
- ANALYSIS OF NEUTRONICS SAFETY PARAMETERS AND CORE BURNUP LIFETIME OF BAEC TRIGA MARK-II RESEARCH REACTOR USING THE DETERMINISTIC TRIGAP AND TRIGLAV CODES
- OPENMC-BASED NEUTRONIC ANALYSIS OF METALLIC-FUELED ABR-1000 SODIUM-COOLED FAST REACTOR /
- MACHINE LEARNING APPROACHES FOR DRAGON FRUIT YIELD PREDICTION IN BANGLADESH /
- ENHANCING THE ACCIDENT TOLERANCE OF VVER-1200 FUEL ASSEMBLIES USING NANOPARTICLE-REINFORCED CLADDING: A COUPLED NEUTRONIC- THERMAL MULTIPHYSICS STUDY/
- Neutron Scattering in Biology /
- Professional Assembly Language /
Téma: Nuclear Science and Engineering
- ANALYSIS OF A PROBABILISTIC FRACTURE MECHANICS CODE FOR PRESSURIZED WATER REACTOR /
- AN INVESTIGATION OF WATER CHARACTERISTICS IN THERMAL AND NUCLEAR POWER PLANTS /
- DESIGN AND DEVELOPMENT OF A LOW COST AIRBORNE RADIATION MAPPING SYSTEM USING UNMANNED AERIAL VEHICLE (UAV) /
- THERMO-MECHANICAL ANALYSIS OF VARIABLE VISCOSITY FLUID MIXING IN T-JUNCTIONS FOR NUCLEAR FACILITIES /
- A NUMERICAL APROACH TO DESIGN AND DEVELOP PHYSICAL PROTECTION SYSTEM OF A NUCLEAR INSTALLATION /
- A STUDY ON CORE NEUTRONIC PARAMETERS OF THERMAL (BEAVRS PWR) AND FAST (NEA SFR) REACTORS USING MONTE CARLO CODES /
Téma: This Thesis Paper of NSE in BSc Program.
- REACTOR THERMAL HYDRAULICS ANALYSIS OF NUSCALE SUBCHANNEL USING ALUMINA NANOFLUID /
- THERMO-MECHANICAL ANALYSIS OF VARIABLE VISCOSITY FLUID MIXING IN T-JUNCTIONS FOR NUCLEAR FACILITIES /
- 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 /