相似書籍: FRACTURE MECHANICS ANALYSIS OF A PWR REACTOR COOLANT SYSTEM (rcs) PIPING /
- COMPATIBILITY ANALYSIS OF STRUCTURAL MATERIALS USED IN REACTOR COOLANT PIPING SYSTEMS USING ANSYS AND OPENMCE /
- FAILURE PROBABILITY ANALYSIS OF A PWR PRESSURE VESSEL NOZZLE BY USING PROBABILISTIC FRACTURE MECHANICS CODE /
- ANALYSIS OF A PROBABILISTIC FRACTURE MECHANICS CODE FOR PRESSURIZED WATER REACTOR /
- FAILURE PROBABILITY ASSESSMENT OF A PWR PRESSURE VESSEL NOZZLE UNDER IRRADIATED CONDITION BY APPLYING FRACTURE MECHANICS ANALYSIS /
- NEUTRONIC ASSESSMENT AND THERMAL HYDRAULIC MODELING OF COATED FUEL CLADDING AND NANOFLUID COOLANTS IN A VVER-1200 REACTOR/
- A STUDY ON CORE NEUTRONIC PARAMETERS OF THERMAL (BEAVRS PWR) AND FAST (NEA SFR) REACTORS USING MONTE CARLO CODES /
主題: Nuclear Science Engineering.
- DESIGN AND DEVELOPMENT OF A ROBOTIC SYSTEM FOR RADIATION DETECTION AND MEASUREMENT /
- ANALYSIS OF NEUTRONICS SAFETY PRAMETERS AND CORE BURNUP LIFETIME OF BAEC TRIGA MARK-II RESEARCH REACTOR USING THE DETERMINISTIC TRIGAP AND TRIGLAV CODES /
- FAILURE PROBABILITY ASSESSMENT OF A PWR PRESSURE VESSEL NOZZLE UNDER IRRADIATED CONDITION BY APPLYING FRACTURE MECHANICS ANALYSIS /
- FRACTURE MECHANICS ANALYSIS OF A PWR REACTOR COOLANT SYSTEM (rcs) PIPING /
- DESIGN AND SAFETY ANALYSIS OF A NAVAL REACTOR FOR NUCLEAR POWERED SHIP /
主題: This Thesis Paper of NSE in B.Sc. Program.
- 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 /
- FAILURE PROBABILITY ASSESSMENT OF A PWR PRESSURE VESSEL NOZZLE UNDER IRRADIATED CONDITION BY APPLYING FRACTURE MECHANICS ANALYSIS /
- FRACTURE MECHANICS ANALYSIS OF A PWR REACTOR COOLANT SYSTEM (rcs) PIPING /
- PERFORMANCE STUDY AND APPLICATION OF HIGH PURITY GERMANIUM DETECTOR SYSTEM FOR NATURAL RADIOACTIVITY MEASUREMENTS /