REACTOR THERMAL HYDRAULICS ANALYSIS OF NUSCALE SUBCHANNEL USING ALUMINA NANOFLUID /
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| פורמט: | ספר |
| שפה: | אנגלית |
| יצא לאור: |
Dhaka :
NSE DEPT. MIST,
c2026.
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אין תגיות, היה/י הראשונ/ה לתייג את הרשומה!
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פריטים דומים: REACTOR THERMAL HYDRAULICS ANALYSIS OF NUSCALE SUBCHANNEL USING ALUMINA NANOFLUID /
- INTEGRATED SUBCHANNEL AND CONJUGATE HEAT TRANSFER ANALYSIS OF NUSCALE TYPE SMALL MODULAR REACTOR /
- NEUTRONIC ASSESSMENT AND THERMAL HYDRAULIC MODELING OF COATED FUEL CLADDING AND NANOFLUID COOLANTS IN A VVER-1200 REACTOR/
- ENHANCEMENT OF A PRESSURIZED WATER REACTOR SUBCHANNEL DESIGN TO MAXIMIZE HEAT TRANSFER EFFICIENCY /
- ANALYSIS OF STRUCTURAL SAFETY PARAMETERS AND THERMAL BEHAVIOR OF THE FUEL ASSEMBLY OF A GENERIC VVER-1200 NUCLEAR REACTOR USING ANSYS /
- A STUDY ON CORE NEUTRONIC PARAMETERS OF THERMAL (BEAVRS PWR) AND FAST (NEA SFR) REACTORS USING MONTE CARLO CODES /
- Nuclear Reactor Thermal Hydraulics : An Introduction to Nuclear Heat Transfer and Fluid Flow /