Effect of interface undulation on the high temperature oxidation behaviors of grit-blasted and coated zircaloy in pressurized water

2021 ◽  
Vol 192 ◽  
pp. 109839
Author(s):  
Dongliang Jin ◽  
Jishen Jiang ◽  
Zhengxian Di ◽  
Cheng Zhang ◽  
Mei Xiong ◽  
...  
Keyword(s):  
High Temperature ◽  
High Temperature Oxidation ◽  
Pressurized Water ◽  
Temperature Oxidation ◽  
Oxidation Behaviors

High Temperature Oxidation Behaviors of Fe-Cr-Al Based Powder Porous Metal and a Strip

2013 ◽  
Vol 51 (10) ◽  
pp. 743-751 ◽  
Author(s):  
Seon-Hui Lim ◽  
Jae-Sung Oh ◽  
Young-Min Kong ◽  
Byung-Kee Kim ◽  
Man-Ho Park ◽  
...  
Keyword(s):  
High Temperature ◽  
High Temperature Oxidation ◽  
Porous Metal ◽  
Temperature Oxidation ◽  
Oxidation Behaviors

Study on High-Temperature Oxidation Behaviors of Plasma-Sprayed TiB2-Co Composite Coatings

2018 ◽  
Vol 55 (2) ◽  
pp. 178-184 ◽  
Author(s):  
Milad Fadavi ◽  
Amin Rabiei Baboukani ◽  
Hossein Edris ◽  
Mahdi Salehi
Keyword(s):  
High Temperature ◽  
High Temperature Oxidation ◽  
Composite Coatings ◽  
Temperature Oxidation ◽  
Plasma Sprayed ◽  
Oxidation Behaviors

High-Temperature Oxidation Modeling of New Perspective Accident Tolerant Fuel Claddings

2019 ◽  
Author(s):  
Alexander Vasiliev
Keyword(s):  
High Temperature ◽  
High Temperature Oxidation ◽  
Power Plants ◽  
Renewable Energy Sources ◽  
Nuclear Industry ◽  
Safety Level ◽  
Pressurized Water ◽  
Temperature Oxidation ◽  
Design Basis ◽  
New Perspective

Abstract Currently, the comprehension among the specialists and functionaries is getting stronger that the nuclear industry can encounter serious difficulties in development in the case of insufficiently decisive measures to enhance the safety level of nuclear objects. The keen competition with renewable energy sources like wind, solar or geothermal energy takes place presently and is expected to continue in future decades. One of main measures of nuclear safety enhancement could be the drastic renovation of materials used in nuclear industry. The analytical models of high-temperature oxidation of new perspective materials including chromium-nickel-based alloys, zirconium-based cladding with protective chromium coating, FeCrAl alloys and composite claddings on the basis of SiC/SiC in the course of design-basis and beyond-design-basis accidents at nuclear power plants (NPPs) are developed and implemented to severe accident computer running code. The comparison with available experimental data is conducted. The preliminary calculations of nuclear pressurized water reactor loss-of-coolant accidents with new types of claddings demonstrate encouraging results for hydrogen generation rate and integral hydrogen production. It looks optimistic for considerable upgrade of safety level for future generation NPPs using new fuel and cladding materials.

Sign in / Sign up

Export Citation Format

Share Document