Samankaltaisia teoksia: FAILURE PROBABILITY ANALYSIS OF A PWR PRESSURE VESSEL NOZZLE BY USING PROBABILISTIC FRACTURE MECHANICS CODE /
- 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 /
- 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 /
- A STUDY ON CORE NEUTRONIC PARAMETERS OF THERMAL (BEAVRS PWR) AND FAST (NEA SFR) REACTORS USING MONTE CARLO CODES /
- STUDY AND ANALYTICAL RESPONSE OF VVER-1200 AND 3-LOOP PWR (100 MW) TO THE TRANSIENT: LARGE-BREAK LOCA IN COLD LEG USING LEG USING PCTRAN /
Aihe: Nuclear Science and Engineering.
- 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 /
- QUALITY AND ELEMENTAL CHARACTERIZATION OF COMMON SPICES OF BANGLADESH USING NUCLEAR REACTOR -BASED NAA AND GAMMA IRRADIATION TECHNIQUES /
- A CROWDSOURCED APPROACH FOR SUPPLY CHAIN NETWORK OPTIMIZATION USING HUB AND SPOKE MODE3L /
- ANALYSIS OF A PROBABILISTIC FRACTURE MECHANICS CODE FOR PRESSURIZED WATER REACTOR /
- AN INVESTIGATION OF WATER CHARACTERISTICS IN THERMAL AND NUCLEAR POWER PLANTS /
Aihe: 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 /
- NEUTRONIC ANALYSIS WITH GADOLINIUM AND ERBIUM AS BURNABLE ABSORBERS IN GENERIC VVER-1200 /
- FAILURE PROBABILITY ANALYSIS OF A PWR PRESSURE VESSEL NOZZLE BY USING PROBABILISTIC FRACTURE MECHANICS CODE /
- 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 /