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Keyword [Fuel cladding]
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1. The Effect Of Primary Water Chemistry On The Integrity Of Nuclear Fuel Cladding Tube
2. Research On High Temperature Mechanical Property And Irradiation Performance Of C276Alloy As Candidate Material For The Fuel Cladding In Supercritical Water Reactor (SCWR)
3. Study On Creep Behaviors Of C276as One Of The Candidate Materials For The Fuel Cladding Of Supercritical Water Reactor At High Temperature
4. Study Of The Influencing Factors Of The Thickness Measurement For Fuel Cladding In MCNP
5. The Numerical Heat Transfer Research On SiC Composites Used On The Advanced Fuel Rod
6. Corrosion Behavior Of Candidate Fuel Cladding Materials For Supercritical Water-cooled Reactor
7. Low Cycle Fatigue Behavior Of 15-15ti Austenitic Stainless Steel In Lead-Bismuth Eutectic
8. Simulation Of CORA&QUENCH Severe Fuel Damage Experiments And Development Of Cladding Oxidation & Hydrogen Release Models
9. Multiscale Simulation Study For Mechanical And Thermal Properties Of UO2-FeCrAl Fuel-cladding System
10. The Study Of Thermo-Mechanical Properties For Multilayer Silicon Carbide Cladding In PWR
11. Effects Of Zr And/or Ti Addition On The Nano-scale Particles In ODS Steels As The Fuel Cladding Materials Of Generation Iv Nuclear Fission Reactors
12. Study On High-entropy Alloy AlCrCuFe(Mo_x,Nb_x) For Nuclear Fuel Cladding
13. Investigation Of Irradiation Behavior And Corrosion Properties Of Nuclear Grade FeCrAl Alloys
14. Multi-Physics Coupling Simulation Within Porous CRUD Deposits On PWR Fuel Cladding
15. Geometrically-accurate and homogenized fuel region models to predict fuel cladding temperatures within a truck cask under normal and fire accident conditions
16. Mechanical Characterization of SiCF-SiCM Nuclear Fuel Cladding by a Novel Hydraulic Internal Pressurization Method
17. Research On Gap-to-coolant Release Of Fission Gas In Pressurized Water Reactor Under The Condition Of Fuel Cladding Breach
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