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

Na minha lista:

Detalhes bibliográficos
Autor principal:	Bejoy, Md. Mehedi Hasan
Autor Corporativo:	Supervised by Dr. Md. Azizur Rahman (Professor, Dept of NSE, MIST,Dhaka)
Outros Autores:	Saifuddin, Md, Islam, Md. Tonurul
Formato:	Livro
Idioma:	inglês
Publicado em:	Dhaka : NSE DEPT. MIST, c2026.
Assuntos:	Nuclear Science and Engineering. This Thesis Paper of NSE in BSc Program.
Tags:	Adicionar Tag Sem tags, seja o primeiro a adicionar uma tag!

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

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