NUMERICAL INVESTIGATION OF TURBULENT NATURAL CONVECTION IN AN SFR CORE CATCHER /

Tallennettuna:

Bibliografiset tiedot
Päätekijä:	Bejoy, Md. Mehedi Hasan
Yhteisötekijä:	Supervised by Dr. Md. Azizur Rahman (Professor, Dept of NSE, MIST,Dhaka)
Muut tekijät:	Saifuddin, Md, Islam, Md. Tonurul
Aineistotyyppi:	Kirja
Kieli:	englanti
Julkaistu:	Dhaka : NSE DEPT. MIST, c2026.
Aiheet:	Nuclear Science and Engineering. This Thesis Paper of NSE in BSc Program.
Tagit:	Lisää tagi Ei tageja, Lisää ensimmäinen tagi!

Samankaltaisia teoksia: NUMERICAL INVESTIGATION OF TURBULENT NATURAL CONVECTION IN AN SFR CORE CATCHER /

Pikavilkaisu
A STUDY ON CORE NEUTRONIC PARAMETERS OF THERMAL (BEAVRS PWR) AND FAST (NEA SFR) REACTORS USING MONTE CARLO CODES /
Pikavilkaisu
MEASUREMENT OF REACTIVITY OF THE FUEL AND CORE EXCESS REACTIVITY OF THE BTRR /
Pikavilkaisu
HEALTH RISK ASSESSMENT BY INVESTIGATING NATURAL RADIONUCLIDES AND HEAVY METAL PRESENCE IN SURFACE WATER /
Pikavilkaisu
ASSESSMENT OF NATURAL RADIONUCLIDES AND HEAVY METALS IN SOIL SAMPLES OF JAMUNA RIVER BASIN, BANGLADESH /
Pikavilkaisu
PERFORMANCE STUDY AND APPLICATION OF HIGH PURITY GERMANIUM DETECTOR SYSTEM FOR NATURAL RADIOACTIVITY MEASUREMENTS /
Pikavilkaisu
AN INVESTIGATION OF WATER CHARACTERISTICS IN THERMAL AND NUCLEAR POWER PLANTS /
Pikavilkaisu
A COMPARATIVE ANALYSIS OF GEOMETRY DEFECTS AFFECTING DIMENSIONAL ACCURACY BY NON-DESTRUCTIVE TESTING (NDT) METHODS /
Pikavilkaisu
FAILURE PROBABILITY ANALYSIS OF A PWR PRESSURE VESSEL NOZZLE BY USING PROBABILISTIC FRACTURE MECHANICS CODE /
Pikavilkaisu
A NUMERICAL APROACH TO DESIGN AND DEVELOP PHYSICAL PROTECTION SYSTEM OF A NUCLEAR INSTALLATION /
Pikavilkaisu
ANALYSIS OF NEUTRON IRRADIATION EMBRITTLEMENT OF VVER 1200 REACTOR PRESSURE VESSEL WALL /
Pikavilkaisu
REACTOR THERMAL HYDRAULICS ANALYSIS OF NUSCALE SUBCHANNEL USING ALUMINA NANOFLUID /
Pikavilkaisu
THERMO-MECHANICAL ANALYSIS OF VARIABLE VISCOSITY FLUID MIXING IN T-JUNCTIONS FOR NUCLEAR FACILITIES /
Pikavilkaisu
OPENMC-BASED NEUTRONIC ANALYSIS OF METALLIC-FUELED ABR-1000 SODIUM-COOLED FAST REACTOR /
Pikavilkaisu
CONCEPTUAL DESIGN OF VVER-1200 SPENT NUCLEAR FUEL DRY STORAGE CASK : A NEUTRONIC, RADIATION SHIELDING AND THERMAL ANALYSIS /
Pikavilkaisu
NEUTRONIC ASSESSMENT AND THERMAL HYDRAULIC MODELING OF COATED FUEL CLADDING AND NANOFLUID COOLANTS IN A VVER-1200 REACTOR/
Pikavilkaisu
ENHANCING THE ACCIDENT TOLERANCE OF VVER-1200 FUEL ASSEMBLIES USING NANOPARTICLE-REINFORCED CLADDING: A COUPLED NEUTRONIC- THERMAL MULTIPHYSICS STUDY/
Pikavilkaisu
ANALYSIS OF GAMMA-INDUCED LEMON LEAF MUTANT DEVELOPED VIA LEAF CUT TECHNIQUE THROUGH VISUAL INSPECTION AND DENDROGRAM /
Pikavilkaisu
INTEGRATED SUBCHANNEL AND CONJUGATE HEAT TRANSFER ANALYSIS OF NUSCALE TYPE SMALL MODULAR REACTOR /
Pikavilkaisu
NEUTRONICS CHARACTERISTICS ANALYSIS OF ALFRED WITH LFR REFLECTOR COMPARISON AND CONCEPTUAL MPRR USING OPENMC /
Pikavilkaisu
COMPREHENSIVE ANALYSIS OF HEAVY METALS IN POULTRY CHICKEN FEEDS BY ATOMIC ABSORPTION SPECTROSCOPY /
Pikavilkaisu
NEUTRONIC PARAMETERS AND BURNUP ANALYSIS OF FRESH FUEL ASSEMBLIES OF WER-1000 KALININ-1 NPP USING THE DETERMINISTIC CODE DRAGONS /
Pikavilkaisu
ANALYSIS OF SHIELD DESIGN ASPECT OF SEMI-INDUSTRIAL COBALT 60 GAMA IRRADIATION FACILITY AT IRPT BY MICRO-SHEILD 5.05 AND QAD-CGGP2 /
Pikavilkaisu
ANALYSIS OF STRUCTURAL SAFETY PARAMETERS AND THERMAL BEHAVIOR OF THE FUEL ASSEMBLY OF A GENERIC VVER-1200 NUCLEAR REACTOR USING ANSYS /
Pikavilkaisu
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 /