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Keyword [Alloy 690]
Result: 1 - 10 | Page: 1 of 1
1.
Investigation On Corrosion Resistance Of Alloy 690 Steam Generator Heat Exchange Tube
2.
Corrosion Of Heat Exchange Tube For PWR Steam Generators
3.
Corrosion Fatigue Behavior Of Nuclear-grade Austenitic Alloys In High Temperature And High Pressure Water
4.
Researches On Impact Fretting Wear Of Alloy 690 Tubes With Line Contact In Dry State
5.
Study On Characteristics Of Fretting Wear Of Alloy 690 Tube With Plasma Spraying WC-12Co Coating
6.
High-temperature Corrosion Behaviors Of Alloy 690 Heat Exchange Tube For Steam Generators
7.
Research On Laser Surface Modification Of Alloy 690 Tube For Nuclear Power Steam Generator
8.
Fretting Fatigue And Notch Fatigue Of Nuclear-grade Austenitic Alloys In High-temperature Pressurized Water
9.
The Influence Of Grain Boundary And Triple Junction Type On The Carbide Precipitation In Inconel Alloy 690
10.
Research On The Fatigue Behavior Of Nickel Based Alloy 690 And Its Welds For Nuclear Power Plant
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