Documenti analoghi: ANALYSIS OF SHIELD DESIGN ASPECT OF SEMI-INDUSTRIAL COBALT 60 GAMA IRRADIATION FACILITY AT IRPT BY MICRO-SHEILD 5.05 AND QAD-CGGP2 /
- Cobalt-base alloys for biomedical applications /
- Radiation Shielding and Radiological Protection /
- Visual basic 6.0 programming /
- Shielding Techniques for Radiation Oncology Facilities /
- Programming in Visual Basic, version 6.0 /
- ANALYSIS OF NEUTRON IRRADIATION EMBRITTLEMENT OF VVER 1200 REACTOR PRESSURE VESSEL WALL /
Soggetto: 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 /
Soggetto: This Thesis Paper of NSE in BSc Program.
- REACTOR THERMAL HYDRAULICS ANALYSIS OF NUSCALE SUBCHANNEL USING ALUMINA NANOFLUID /
- THERMO-MECHANICAL ANALYSIS OF VARIABLE VISCOSITY FLUID MIXING IN T-JUNCTIONS FOR NUCLEAR FACILITIES /
- NUMERICAL INVESTIGATION OF TURBULENT NATURAL CONVECTION IN AN SFR CORE CATCHER /
- OPENMC-BASED NEUTRONIC ANALYSIS OF METALLIC-FUELED ABR-1000 SODIUM-COOLED FAST REACTOR /
- ASSESSMENT OF NATURAL RADIONUCLIDES AND HEAVY METALS IN SOIL SAMPLES OF JAMUNA RIVER BASIN, BANGLADESH /
- CONCEPTUAL DESIGN OF VVER-1200 SPENT NUCLEAR FUEL DRY STORAGE CASK : A NEUTRONIC, RADIATION SHIELDING AND THERMAL ANALYSIS /