Effects of pH on lead-induced passivity degradation of nuclear steam generator tubing alloy in high temperature crevice chemistries

2013 ◽  
Vol 87 ◽  
pp. 824-838 ◽  
Author(s):  
B.T. Lu ◽  
J.L. Luo ◽  
Y.C. Lu
Keyword(s):  
High Temperature ◽  
Steam Generator ◽  
Steam Generator Tubing ◽  
Effects Of Ph

scholarly journals Numerical discretization analysis of a HTR steam generator model for the thermal-hydraulics code trace

2014 ◽  
Vol 29 (suppl.) ◽  
pp. 31-38 ◽  
Author(s):  
Markus Esch ◽  
Dietrich Knoche ◽  
Antonio Hurtado
Keyword(s):  
High Temperature ◽  
Steam Generator ◽  
Electricity Production ◽  
Thermal Hydraulics ◽  
The Past ◽  
Crucial Component ◽  
High Temperature Reactor ◽  
Different Diameters ◽  
Typical Design ◽  
Steam Generator Model

For future high temperature reactor projects, e. g., for electricity production or nuclear process heat applications, the steam generator is a crucial component. A typical design is a helical coil steam generator consisting of several tubes connected in parallel forming cylinders of different diameters. This type of steam generator was a significant component used at the thorium high temperature reactor. In the work presented the temperature profile is being analyzed by the nodal thermal hydraulics code TRACE for the thorium high temperature reactor steam generator. The influence of the nodalization is being investigated within the scope of this study and compared to experimental results from the past. The results of the standard TRACE code are compared to results using a modified Nusselt number for the primary side. The implemented heat transfer correlation was developed within the past German HTR program. This study shows that both TRACE versions are stable and provides a discussion of the nodalization requirements.

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