Science and Technology of Nuclear Installations

Research Article

Analysis of Density Wave Oscillations in Helically Coiled Tube Once-Through Steam Generator

Table 1

Heat transfer correlations in the tube side and shell side of H-OTSG.
CorrelationsExperimental parameters
Tube side [13] 
 Single-phase region:  
   
 
80 < < 3000 kg/(m2·s)
 Critical Reynolds number [14]: 

 
 Nucleate boiling region: 
0.1 < < 20 MPa
80 < < 3000 kg/(m2·s)
60 < < 800 kW/m2 

 
 , 
, 
 Postdryout region: 
0.1 < < 21.5 MPa
100 < < 2000 kg/(m2·s) 

  
, 
 
Shell side [13]: 
 
 
0.1 < < 20 MPa