A STUDY ON CORE NEUTRONIC PARAMETERS OF THERMAL (BEAVRS PWR) AND FAST (NEA SFR) REACTORS USING MONTE CARLO CODES /
সংরক্ষণ করুন:
| প্রধান লেখক: | |
|---|---|
| সংস্থা লেখক: | |
| বিন্যাস: | গ্রন্থ |
| ভাষা: | ইংরেজি |
| প্রকাশিত: |
Dhaka :
NSE DEPT. MIST,
c2025.
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| বিষয়গুলি: | |
| ট্যাগগুলো: |
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অনুরূপ উপাদানগুলি: A STUDY ON CORE NEUTRONIC PARAMETERS OF THERMAL (BEAVRS PWR) AND FAST (NEA SFR) REACTORS USING MONTE CARLO CODES /
- NUMERICAL INVESTIGATION OF TURBULENT NATURAL CONVECTION IN AN SFR CORE CATCHER /
- OPENMC-BASED NEUTRONIC ANALYSIS OF METALLIC-FUELED ABR-1000 SODIUM-COOLED FAST REACTOR /
- ANALYSIS OF NEUTRON IRRADIATION EMBRITTLEMENT OF VVER 1200 REACTOR PRESSURE VESSEL WALL /
- NEUTRONIC ASSESSMENT AND THERMAL HYDRAULIC MODELING OF COATED FUEL CLADDING AND NANOFLUID COOLANTS IN A VVER-1200 REACTOR/
- ANALYSIS OF STRUCTURAL SAFETY PARAMETERS AND THERMAL BEHAVIOR OF THE FUEL ASSEMBLY OF A GENERIC VVER-1200 NUCLEAR REACTOR USING ANSYS /
- NEUTRONIC PARAMETERS AND BURNUP ANALYSIS OF FRESH FUEL ASSEMBLIES OF WER-1000 KALININ-1 NPP USING THE DETERMINISTIC CODE DRAGONS /