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Keyword [Fuel cladding]
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1. Impact Wear Properties And Wear Mechanism Of Zr-4 Alloy Tube And Inconel718
2. Composition Optimization And High-Temperature Microstructural Stabilities Of Stainless Steels For Nuclear Fuel Cladding Materials
3. Experimental Investigation On Boiling Heat Transfer On High-temperature Accident Tolerant Fuel Cladding Surface
4. Fabrication And Properties Of Steels For Fuel Cladding Tube In Lead-cooled Fast Reactor
5. The Research Of The Unstable Fission Gas Release Under The Condition Of Fuel Clad Breached
6. Influence of oxide microstructure on corrosion behavior of zirconium-based model alloys
7. Ceramic Coatings for Nuclear Fuel Cladding to Enhance Accident Toleranc
8. Pellet cladding mechanical interactions of ceramic claddings fuels under light water reactor conditions
9. Fracture toughness behavior of Zircaloy-4 in the form of fuel cladding tubing in nuclear reactors
10. Monitoring the Progress of Damage in a SiCF-SiC M Composite Nuclear Fuel Cladding Under Internal Pressure Using Acoustic Emissio
11. Effect Of Zr,Nb And Mo On Microstructure Evolution And Properties Of Fe-Cr-Al Alloys For Nuclear Fuel Cladding
12. The Preparation Technology,Microstructure And Properties Of FeCrAl Alloy For Nuclear Fuel Cladding
13. Preparation And Properties Of FeCrAl Accident-Tolerant Fuel Cladding
14. Investigation Of Microstructure,Properties And In-situ Ion Irradiation Behavior Of Cr Coated Zr-4 Alloy Prepared By Electroplating
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