scholarly journals Thermal hydraulics of steam generator sludge

Author(s):  
A. Ulke
2014 ◽  
Vol 29 (suppl.) ◽  
pp. 31-38 ◽  
Author(s):  
Markus Esch ◽  
Dietrich Knoche ◽  
Antonio Hurtado

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.


2020 ◽  
Vol 136 ◽  
pp. 107020 ◽  
Author(s):  
Xi Wang ◽  
Mingjun Wang ◽  
Ge Wu ◽  
Jing Zhang ◽  
Suizheng Qiu ◽  
...  

2017 ◽  
Vol 105 ◽  
pp. 282-301 ◽  
Author(s):  
Santiago F. Corzo ◽  
Dario M. Godino ◽  
Norberto M. Nigro ◽  
Damian E. Ramajo

Author(s):  
Blazenka Maslovaric ◽  
Vladimir Stevanovic ◽  
Sanja Prica ◽  
Zoran Stosic

The tube rupture accident is one among the most risk-dominant events at the nuclear power plants. Several steam generator tube rupture accidents have occurred at the plants in the past. In this paper the Computational Multi-Fluid Dynamics (CMFD) investigation of the horizontal steam generator thermal-hydraulics during the tube rupture accident is performed. A guillotine of a steam generator U-tube is assumed with choked flow from the primary to the secondary side of the steam generator. Predicted are water and steam velocity fields, steam volume fraction distribution on the steam generator secondary (shell) side, as well as the swell level increase. Obtained multidimensional results are a support to the safety analyses of the steam generator tube rupture accident. Also, they serve as benchmark tests for an assessment of the applicability of one-dimensional horizontal steam generator models, developed by standard safety codes. Numerical simulation is performed with the multidimensional multi-fluid modelling approach. The two-phase flow around steam generator tubes in the bundle is modelled by the porous media approach. Interfacial mass, momentum and energy transfer is modelled with the closure laws, where some of them are specially developed for the conditions of the two-phase flow across tube bundles. The governing equations are solved with the SIMPLE type pressure-correction method that is derived for the conditions of multi-phase flow conditions.


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