Ítems similars: NUMERICAL INVESTIGATION OF TURBULENT NATURAL CONVECTION IN AN SFR CORE CATCHER /
- A STUDY ON CORE NEUTRONIC PARAMETERS OF THERMAL (BEAVRS PWR) AND FAST (NEA SFR) REACTORS USING MONTE CARLO CODES /
- MEASUREMENT OF REACTIVITY OF THE FUEL AND CORE EXCESS REACTIVITY OF THE BTRR /
- HEALTH RISK ASSESSMENT BY INVESTIGATING NATURAL RADIONUCLIDES AND HEAVY METAL PRESENCE IN SURFACE WATER /
- ASSESSMENT OF NATURAL RADIONUCLIDES AND HEAVY METALS IN SOIL SAMPLES OF JAMUNA RIVER BASIN, BANGLADESH /
- PERFORMANCE STUDY AND APPLICATION OF HIGH PURITY GERMANIUM DETECTOR SYSTEM FOR NATURAL RADIOACTIVITY MEASUREMENTS /
- AN INVESTIGATION OF WATER CHARACTERISTICS IN THERMAL AND NUCLEAR POWER PLANTS /
Tema: 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/
Tema: 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 /