Antzeko izenburuak: ANALYSIS OF A PROBABILISTIC FRACTURE MECHANICS CODE FOR PRESSURIZED WATER REACTOR /
- FAILURE PROBABILITY ANALYSIS OF A PWR PRESSURE VESSEL NOZZLE BY USING PROBABILISTIC FRACTURE MECHANICS CODE /
- ANALYSIS OF NEUTRON IRRADIATION EMBRITTLEMENT OF VVER 1200 REACTOR PRESSURE VESSEL WALL /
- STRUCTURAL INTEGRITY ANALYSIS OF VVER-1200 REACTOR VESSEL WALL DUE TO PRESSURIZED THERMAN SHOCK /
- AN INVESTIGATION OF WATER CHARACTERISTICS IN THERMAL AND NUCLEAR POWER PLANTS /
- ENHANCEMENT OF A PRESSURIZED WATER REACTOR SUBCHANNEL DESIGN TO MAXIMIZE HEAT TRANSFER EFFICIENCY /
- QUALITY AND ELEMENTAL CHARACTERIZATION OF COMMON SPICES OF BANGLADESH USING NUCLEAR REACTOR -BASED NAA AND GAMMA IRRADIATION TECHNIQUES /
Gaia: Thesis Paper of NSE in M.Sc Prog.
Gaia: 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 /