The modeling and simulation of the thermal conductivity of irradiated U-Mo dispersion fuel: Estimation of the thermal conductivity of the interaction layer

2018 ◽  
Vol 510 ◽  
pp. 199-209 ◽  
Author(s):  
Qusai M. Mistarihi ◽  
Jun Teak Hwang ◽  
Ho Jin Ryu
2015 ◽  
Vol 458 ◽  
pp. 380-393 ◽  
Author(s):  
A. Leenaers ◽  
S. Van den Berghe ◽  
E. Koonen ◽  
V. Kuzminov ◽  
C. Detavernier

2016 ◽  
Vol 473 ◽  
pp. 309-319 ◽  
Author(s):  
Douglas E. Burkes ◽  
Tanja K. Huber ◽  
Andrew M. Casella

2015 ◽  
Vol 466 ◽  
pp. 576-582 ◽  
Author(s):  
Yeon Soo Kim ◽  
Byoung Jin Cho ◽  
Dong-Seong Sohn ◽  
Jong Man Park

2013 ◽  
Vol 721 ◽  
pp. 184-189
Author(s):  
Xiao Liu ◽  
Da Zhi Qian ◽  
Zhi Hua Zhang ◽  
Bin Tang

UMo/Al fuel is a typical dispersion fuel and is becoming a focus of research in many countries as it has higher density, better thermal conductivity and stronger irradiation resistance. According to the structure characteristics of dispersion nuclear fuel, the periodic unit model is established and the mechanical behavior for UMo/Al dispersion fuel on different fuel volume and burnup is simulated by ANSYS software. The results show that maximum stress occurs in the middle of fuel plate. With the fuel volume fraction increasing, the risk of rupture of fuel plate corresponding increase. It reveal the mechanism of irradiation failure for dispersion fuel plate and the results can be demonstrated by the sample figure of irradiation.


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