MEASUREMENT OF REACTIVITY OF THE FUEL AND CORE EXCESS REACTIVITY OF THE BTRR /

Sábháilte in:

Sonraí bibleagrafaíochta
Príomhchruthaitheoir:	Sami, Absar Hanzala
Údair chorparáideacha:	Supervised by Col. Molla Md. Zubaer (Dept. of R & D, MIST.), Co-Supervised by Dr. Md. Abdul Malek Soner, Director and Chief Scientific Officer, AERE, BAEC, Savar, Dhaka
Rannpháirtithe:	Sami, Albab Huzaifa
Formáid:	LEABHAR
Teanga:	Béarla
Foilsithe / Cruthaithe:	Dhaka : NSE DEPT. MIST, c2024.
Ábhair:	Nuclear Science and Engineering. This Thesis Paper of NSE in B.Sc. Program.
Clibeanna:	Cuir clib leis Níl clibeanna ann, Bí ar an gcéad duine le clib a chur leis an taifead seo!

Míreanna comhchosúla: MEASUREMENT OF REACTIVITY OF THE FUEL AND CORE EXCESS REACTIVITY OF THE BTRR /

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MEASUREMENT OF REACTIVITY OF THE FUEL AND CORE EXCESS REACTIVITY OF THE BTRR
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A STUDY ON CORE NEUTRONIC PARAMETERS OF THERMAL (BEAVRS PWR) AND FAST (NEA SFR) REACTORS USING MONTE CARLO CODES /
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OPENMC-BASED NEUTRONIC ANALYSIS OF METALLIC-FUELED ABR-1000 SODIUM-COOLED FAST REACTOR /
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NEUTRONIC ASSESSMENT AND THERMAL HYDRAULIC MODELING OF COATED FUEL CLADDING AND NANOFLUID COOLANTS IN A VVER-1200 REACTOR/
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CONCEPTUAL DESIGN OF VVER-1200 SPENT NUCLEAR FUEL DRY STORAGE CASK : A NEUTRONIC, RADIATION SHIELDING AND THERMAL ANALYSIS /
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NEUTRONIC PARAMETERS AND BURNUP ANALYSIS OF FRESH FUEL ASSEMBLIES OF WER-1000 KALININ-1 NPP USING THE DETERMINISTIC CODE DRAGONS /
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ANALYSIS OF STRUCTURAL SAFETY PARAMETERS AND THERMAL BEHAVIOR OF THE FUEL ASSEMBLY OF A GENERIC VVER-1200 NUCLEAR REACTOR USING ANSYS /
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ENHANCING THE ACCIDENT TOLERANCE OF VVER-1200 FUEL ASSEMBLIES USING NANOPARTICLE-REINFORCED CLADDING: A COUPLED NEUTRONIC- THERMAL MULTIPHYSICS STUDY/
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MEASUREMENT OF BACKSCATTERING FACTOR FOR X RAY CALIBRATION BEAM WITH VARIOUS PHANTOMS USING IONIZATION CHAMBER AND THERMOLUMINESCENT DOSIMETER /
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NEUTRONIC ANALYSIS WITH GADOLINIUM AND ERBIUM AS BURNABLE ABSORBERS IN GENERIC VVER-1200 /
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FAILURE PROBABILITY ANALYSIS OF A PWR PRESSURE VESSEL NOZZLE BY USING PROBABILISTIC FRACTURE MECHANICS CODE /
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COMPATIBILITY ANALYSIS OF STRUCTURAL MATERIALS USED IN REACTOR COOLANT PIPING SYSTEMS USING ANSYS AND OPENMCE /
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ELEMENT ANALYSIS OF RARE EARTH AND HEAVY ELEMENTS OF RIVER JAMUNA BASIN SAND: ENVIRONMENTAL, ANTHROPOGENIC, AND ECONOMIC PERSPECTIVES /
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SYNTHESIS AND CHARACTERIZATION OF DYSPROSIUM DOPED LITHIUM STRONTIUM BORATE FOR DOSIMETRY APPLICATION /
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CONJUGATE HEAT TRANSFER ANALYSIS OF SHELL AND TUBE HEAT EXCHANGER USING ANSYS FLUENT /
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STUDY AND MINERALOGICAL ANALYSIS OF Zr, Ti-RICH MINERALS FOUND IN THE SAND OF COX’S BAZAR COASTAL AREA /
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ENHANCEMENT OF A PRESSURIZED WATER REACTOR SUBCHANNEL DESIGN TO MAXIMIZE HEAT TRANSFER EFFICIENCY /
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PET RADIOPHARMACEUTICALS PRODUCTION PROCEDURES IN A MEDIUM ENERGY CYCLOTRON AT NINMAS, BANGLADESH /
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AN ASSESSMENT AND COMPARISON OF RADIATION DOSE IN PET CT SCANS FOR CANCER PATIENTS /
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REACTOR THERMAL HYDRAULICS ANALYSIS OF NUSCALE SUBCHANNEL USING ALUMINA NANOFLUID /
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THERMO-MECHANICAL ANALYSIS OF VARIABLE VISCOSITY FLUID MIXING IN T-JUNCTIONS FOR NUCLEAR FACILITIES /