Heat conductivity reduction in case of the non-uniform extension of the lattice

2014 ◽  
Vol 4 (1) ◽  
pp. 68-71
Author(s):  
O. I. Savina
2002 ◽  
Vol 58 (5-6) ◽  
pp. 46
Author(s):  
Natal'ya Dmitrievna Sizova ◽  
Victor Filippovich Kravchenko

2017 ◽  
Vol 2017 ◽  
pp. 1-7
Author(s):  
Mazhyn K. Skakov ◽  
Nurzhan Ye. Mukhamedov ◽  
Alexander D. Vurim ◽  
Ilya I. Deryavko

For the first time the paper determines thermophysical properties (specific heat capacity, thermal diffusivity, and heat conductivity) of the full-scale corium of the fast energy nuclear reactor within the temperature range from ~30°С to ~400°С. Obtained data are to be used in temperature fields calculations during modeling the processes of corium melt retention inside of the fast reactor vessel.


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