scholarly journals Development of a fully validated quantitative model of hydride morphology in zirconium alloy nuclear fuel cladding

2017 ◽  
Author(s):  
Pierre -Clement Simon ◽  
Michael Tonks ◽  
Arthur Motta ◽  
Long -Qing Chen
Keyword(s):  
Nuclear Fuel ◽  
Zirconium Alloy ◽  
Quantitative Model ◽  
Fuel Cladding ◽  
Nuclear Fuel Cladding

Creep Tests Research on a New Zirconium Alloy for Nuclear Fuel Cladding Tubes

2012 ◽  
Vol 151 ◽  
pp. 47-51
Author(s):  
Xin Ming Meng ◽  
Fei Xue ◽  
Wei Wei Yu ◽  
Hong Mei Guo
Keyword(s):  
Nuclear Fuel ◽  
Zirconium Alloy ◽  
Axial Direction ◽  
Sem Analysis ◽  
Steady State Creep ◽  
Fuel Cladding ◽  
Steady State Creep Rate ◽  
Creep Life ◽  
Creep Tests ◽  
Nuclear Fuel Cladding

Hoop creep tests and axial creep tests were carried out on a new zirconium alloy for nuclear fuel cladding tubes at 375 °C. The result indicated that the proportion of the second creep stage decreased as the stress increasing, meanwhile, the steady-state creep rate increased in both creep test modes. However, the ability of creep rupture resistance in the hoop direction is more strengthen than that in axial direction. The SEM analysis showed that the creep fracture was mainly dimple toughness fracture. The dimple for low stress was intensive and small. The fitting curve by the θ function was well coincided with the test data, so the creep life can be analyzed by θ function.

scholarly journals Burst Test Research on Zirconium Alloy for Nuclear Fuel Cladding Tubes

2017 ◽  
Vol 46 (6) ◽  
pp. 1491-1496
Author(s):  
Zhang Yanwei ◽  
Wang Rongshan ◽  
Bai Guanghai ◽  
Liu Erwei ◽  
Mei Jinna
Keyword(s):  
Nuclear Fuel ◽  
Zirconium Alloy ◽  
Fuel Cladding ◽  
Burst Test ◽  
Nuclear Fuel Cladding
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