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

में बचाया:

ग्रंथसूची विवरण
मुख्य लेखक:	Sami, Absar Hanzala
निगमित लेखकों:	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
अन्य लेखक:	Sami, Albab Huzaifa
स्वरूप:	पुस्तक
भाषा:	अंग्रेज़ी
प्रकाशित:	Dhaka : NSE DEPT. MIST, c2024.
विषय:	Nuclear Science and Engineering. This Thesis Paper of NSE in B.Sc. Program.
टैग:	टैग जोड़ें कोई टैग नहीं, इस रिकॉर्ड को टैग करने वाले पहले व्यक्ति बनें!

समान संसाधन: MEASUREMENT OF REACTIVITY OF THE FUEL AND CORE EXCESS REACTIVITY OF THE BTRR /

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