Míreanna comhchosúla: AN INVESTIGATION OF WATER CHARACTERISTICS IN THERMAL AND NUCLEAR POWER PLANTS /
- ANALYSIS OF A PROBABILISTIC FRACTURE MECHANICS CODE FOR PRESSURIZED WATER REACTOR /
- HEALTH RISK ASSESSMENT BY INVESTIGATING NATURAL RADIONUCLIDES AND HEAVY METAL PRESENCE IN SURFACE WATER /
- QUALITY AND ELEMENTAL CHARACTERIZATION OF COMMON SPICES OF BANGLADESH USING NUCLEAR REACTOR -BASED NAA AND GAMMA IRRADIATION TECHNIQUES /
- STUDY ON EXPERIMENTAL CROSS SECTIONS FOR REACTIONS 174Yb(n,y)175Yb and 55Mn(n,y)56Mn AT NEW ENTERGIES OF 0.0334 AND 0.0536 eV USING NEUTRONS FROM TRIGA NUCLEAR REACTOR /
- DEVELOPMENT AND CHARACTERIZATION OF PROPERTIES OF HEAVY MINERAL REINFORCED POLYMER COMPOSITE MATERIALS FOR RADIATION SHIELDING PROTECTION /
- MEASUREMENT OF BACKSCATTERING FACTOR FOR X RAY CALIBRATION BEAM WITH VARIOUS PHANTOMS USING IONIZATION CHAMBER AND THERMOLUMINESCENT DOSIMETER /
Topaic: Thesis Paper of NSE in M.sc Prog.
Topaic: 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 /
Údar: Salam, Md. Nur
Údar: Supervised by Dr. Md. Azizur Rahman
- DESIGN OF KRUSTY AND COMPARISON BETWEEN SPACE BASED AND EARTH BASED MICROREACTORS /
- AN INVESTIGATION OF WATER CHARACTERISTICS IN THERMAL AND NUCLEAR POWER PLANTS /
- ENHANCEMENT OF A PRESSURIZED WATER REACTOR SUBCHANNEL DESIGN TO MAXIMIZE HEAT TRANSFER EFFICIENCY /
- NUMERICAL INVESTIGATION OF TURBULENT NATURAL CONVECTION IN AN SFR CORE CATCHER /
- OPENMC-BASED NEUTRONIC ANALYSIS OF METALLIC-FUELED ABR-1000 SODIUM-COOLED FAST REACTOR /