Ejemplares similares: PET RADIOPHARMACEUTICALS PRODUCTION PROCEDURES IN A MEDIUM ENERGY CYCLOTRON AT NINMAS, BANGLADESH /
- AN ASSESSMENT AND COMPARISON OF RADIATION DOSE IN PET CT SCANS FOR CANCER PATIENTS /
- ASSESSMENT OF NATURAL RADIONUCLIDES AND HEAVY METALS IN SOIL SAMPLES OF JAMUNA RIVER BASIN, BANGLADESH /
- INTEGRATED SUBCHANNEL AND CONJUGATE HEAT TRANSFER ANALYSIS OF NUSCALE TYPE SMALL MODULAR REACTOR /
- ENHANCEMENT OF A PRESSURIZED WATER REACTOR SUBCHANNEL DESIGN TO MAXIMIZE HEAT TRANSFER EFFICIENCY /
- A COMPARATIVE ANALYSIS OF GEOMETRY DEFECTS AFFECTING DIMENSIONAL ACCURACY BY NON-DESTRUCTIVE TESTING (NDT) METHODS /
- QUALITY AND ELEMENTAL CHARACTERIZATION OF COMMON SPICES OF BANGLADESH USING NUCLEAR REACTOR -BASED NAA AND GAMMA IRRADIATION TECHNIQUES /
Tópico: Nuclear Science and Engineering.
- QUALITY AND ELEMENTAL CHARACTERIZATION OF COMMON SPICES OF BANGLADESH USING NUCLEAR REACTOR -BASED NAA AND GAMMA IRRADIATION TECHNIQUES /
- ANALYSIS OF A PROBABILISTIC FRACTURE MECHANICS CODE FOR PRESSURIZED WATER REACTOR /
- MEASUREMENT OF BACKSCATTERING FACTOR FOR X RAY CALIBRATION BEAM WITH VARIOUS PHANTOMS USING IONIZATION CHAMBER AND THERMOLUMINESCENT DOSIMETER /
- PERFORMANCE STUDY AND APPLICATION OF HIGH PURITY GERMANIUM DETECTOR SYSTEM FOR NATURAL RADIOACTIVITY MEASUREMENTS /
- DESIGN OF KRUSTY AND COMPARISON BETWEEN SPACE BASED AND EARTH BASED MICROREACTORS /
- COMPATIBILITY ANALYSIS OF STRUCTURAL MATERIALS USED IN REACTOR COOLANT PIPING SYSTEMS USING ANSYS AND OPENMCE /
Tópico: This Thesis Paper of NSE in B.Sc. Program.
- PERFORMANCE STUDY AND APPLICATION OF HIGH PURITY GERMANIUM DETECTOR SYSTEM FOR NATURAL RADIOACTIVITY MEASUREMENTS /
- DESIGN OF KRUSTY AND COMPARISON BETWEEN SPACE BASED AND EARTH BASED MICROREACTORS /
- COMPATIBILITY ANALYSIS OF STRUCTURAL MATERIALS USED IN REACTOR COOLANT PIPING SYSTEMS USING ANSYS AND OPENMCE /
- ELEMENT ANALYSIS OF RARE EARTH AND HEAVY ELEMENTS OF RIVER JAMUNA BASIN SAND: ENVIRONMENTAL, ANTHROPOGENIC, AND ECONOMIC PERSPECTIVES /
- MEASUREMENT OF REACTIVITY OF THE FUEL AND CORE EXCESS REACTIVITY OF THE BTRR /
- NEUTRONIC ANALYSIS WITH GADOLINIUM AND ERBIUM AS BURNABLE ABSORBERS IN GENERIC VVER-1200 /