Torthaí cuardaigh - "Nuclear Science and Engineering."

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  1. 1
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    DESIGN AND DEVELOPMENT OF A LOW COST AIRBORNE RADIATION MAPPING SYSTEM USING UNMANNED AERIAL VEHICLE (UAV) / de réir Abedin, Mohammad Fakhrul

    Foilsithe / Cruthaithe c2022.
    Ábhair: “…Nuclear Science and Engineering.…”
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  2. 2
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    A STUDY ON CORE NEUTRONIC PARAMETERS OF THERMAL (BEAVRS PWR) AND FAST (NEA SFR) REACTORS USING MONTE CARLO CODES / de réir Khan, Mohammad Taha

    Foilsithe / Cruthaithe c2025.
    Ábhair: “…Nuclear Science and Engineering…”
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  3. 3
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    REACTOR THERMAL HYDRAULICS ANALYSIS OF NUSCALE SUBCHANNEL USING ALUMINA NANOFLUID / de réir Ismat, Tabia

    Foilsithe / Cruthaithe c2026.
    Ábhair: “…Nuclear Science and Engineering.…”
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  4. 4
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    THERMO-MECHANICAL ANALYSIS OF VARIABLE VISCOSITY FLUID MIXING IN T-JUNCTIONS FOR NUCLEAR FACILITIES / de réir Shium, Sakib Hossain

    Foilsithe / Cruthaithe c2026.
    Ábhair: “…Nuclear Science and Engineering.…”
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  5. 5
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    NUMERICAL INVESTIGATION OF TURBULENT NATURAL CONVECTION IN AN SFR CORE CATCHER / de réir Bejoy, Md. Mehedi Hasan

    Foilsithe / Cruthaithe c2026.
    Ábhair: “…Nuclear Science and Engineering.…”
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  6. 6
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    OPENMC-BASED NEUTRONIC ANALYSIS OF METALLIC-FUELED ABR-1000 SODIUM-COOLED FAST REACTOR / de réir Bushra, Nilima Huda

    Foilsithe / Cruthaithe c2026.
    Ábhair: “…Nuclear Science and Engineering.…”
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  7. 7
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    ASSESSMENT OF NATURAL RADIONUCLIDES AND HEAVY METALS IN SOIL SAMPLES OF JAMUNA RIVER BASIN, BANGLADESH / de réir Imtiaz, Hasibul Islam

    Foilsithe / Cruthaithe c2026.
    Ábhair: “…Nuclear Science and Engineering.…”
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  8. 8
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    CONCEPTUAL DESIGN OF VVER-1200 SPENT NUCLEAR FUEL DRY STORAGE CASK : A NEUTRONIC, RADIATION SHIELDING AND THERMAL ANALYSIS / de réir Dipto, Roshlan Rahman

    Foilsithe / Cruthaithe c2026.
    Ábhair: “…Nuclear Science and Engineering.…”
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  9. 9
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    NEUTRONIC ASSESSMENT AND THERMAL HYDRAULIC MODELING OF COATED FUEL CLADDING AND NANOFLUID COOLANTS IN A VVER-1200 REACTOR/ de réir Eshat, Fadia Jafrin

    Foilsithe / Cruthaithe c2026.
    Ábhair: “…Nuclear Science and Engineering.…”
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  10. 10
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    ENHANCING THE ACCIDENT TOLERANCE OF VVER-1200 FUEL ASSEMBLIES USING NANOPARTICLE-REINFORCED CLADDING: A COUPLED NEUTRONIC- THERMAL MULTIPHYSICS STUDY/ de réir Nakshi, Purba Meghwati

    Foilsithe / Cruthaithe c2026.
    Ábhair: “…Nuclear Science and Engineering.…”
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  11. 11
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    ANALYSIS OF GAMMA-INDUCED LEMON LEAF MUTANT DEVELOPED VIA LEAF CUT TECHNIQUE THROUGH VISUAL INSPECTION AND DENDROGRAM / de réir Afnan, Jawata

    Foilsithe / Cruthaithe c2025.
    Ábhair: “…Nuclear Science and Engineering…”
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  12. 12
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    INTEGRATED SUBCHANNEL AND CONJUGATE HEAT TRANSFER ANALYSIS OF NUSCALE TYPE SMALL MODULAR REACTOR / de réir Meem, Sadia Islam

    Foilsithe / Cruthaithe c2025.
    Ábhair: “…Nuclear Science and Engineering…”
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  13. 13
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    NEUTRONICS CHARACTERISTICS ANALYSIS OF ALFRED WITH LFR REFLECTOR COMPARISON AND CONCEPTUAL MPRR USING OPENMC / de réir Sunny, Aqueeb Anjum

    Foilsithe / Cruthaithe c2025.
    Ábhair: “…Nuclear Science and Engineering…”
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  14. 14
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    A COMPARATIVE ANALYSIS OF GEOMETRY DEFECTS AFFECTING DIMENSIONAL ACCURACY BY NON-DESTRUCTIVE TESTING (NDT) METHODS / de réir Hasan, Mahadi

    Foilsithe / Cruthaithe c2025.
    Ábhair: “…Nuclear Science and Engineering…”
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  15. 15
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    COMPREHENSIVE ANALYSIS OF HEAVY METALS IN POULTRY CHICKEN FEEDS BY ATOMIC ABSORPTION SPECTROSCOPY / de réir Adiba, Afia

    Foilsithe / Cruthaithe c2025.
    Ábhair: “…Nuclear Science and Engineering…”
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  16. 16
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    ANALYSIS OF SHIELD DESIGN ASPECT OF SEMI-INDUSTRIAL COBALT 60 GAMA IRRADIATION FACILITY AT IRPT BY MICRO-SHEILD 5.05 AND QAD-CGGP2 / de réir Simmy, Nasima Akther

    Foilsithe / Cruthaithe c2025.
    Ábhair: “…Nuclear Science and Engineering…”
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  17. 17
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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 / de réir Shanta, Shah Nusrat Jahan

    Foilsithe / Cruthaithe c2025.
    Ábhair: “…Nuclear Science and Engineering…”
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  18. 18
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    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 / de réir Chowdhury, Fariha

    Foilsithe / Cruthaithe c2025.
    Ábhair: “…Nuclear Science and Engineering…”
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  19. 19
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    NEUTRONIC PARAMETERS AND BURNUP ANALYSIS OF FRESH FUEL ASSEMBLIES OF WER-1000 KALININ-1 NPP USING THE DETERMINISTIC CODE DRAGONS / de réir Ruddra, Aritra Saha

    Foilsithe / Cruthaithe c2025.
    Ábhair: “…Nuclear Science and Engineering…”
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  20. 20
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    A CROWDSOURCED APPROACH FOR SUPPLY CHAIN NETWORK OPTIMIZATION USING HUB AND SPOKE MODE3L /

    Foilsithe / Cruthaithe c2019
    Ábhair: “…Nuclear Science and Engineering…”
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