Title of article :
Conjugate heat transfer simulations of advanced research reactor fuel
Author/Authors :
Piro، نويسنده , , M.H.A. and Leitch، نويسنده , , B.W.، نويسنده ,
Issue Information :
روزنامه با شماره پیاپی سال 2014
Pages :
14
From page :
30
To page :
43
Abstract :
The current work presents numerical simulations of coupled fluid flow and heat transfer of advanced U–Mo/Al and U–Mo/Mg research reactor fuels in support of performance and safety analyses. The objective of this study is to enhance predictions of the flow regime and fuel temperatures through high fidelity simulations that better capture various heat transfer pathways and with a more realistic geometric representation of the fuel assembly in comparison to previous efforts. Specifically, thermal conduction, convection and radiation mechanisms are conjugated between the solid and fluid regions. Also, a complete fuel element assembly is represented in three dimensional space, permitting fluid flow and heat transfer to be simulated across the entire domain. Seven case studies are examined that vary the coolant inlet conditions, specific power, and burnup to investigate the predicted changes in the pressure drop in the coolant and the fuel, clad and coolant temperatures. In addition, an alternate fuel geometry is considered with helical fins (replacing straight fins in the existing design) to investigate the relative changes in predicted fluid and solid temperatures. Numerical simulations predict that the clad temperature is sensitive to changes in the thermal boundary layer in the coolant, particularly in simultaneously developing flow regions, while the temperature in the fuel is anticipated to be unaffected. Finally, heat transfer between fluid and solid regions is enhanced with helical fins, which may be an attractive consideration in future designs to enhance performance and/or safety.
Journal title :
Nuclear Engineering and Design Eslah
Serial Year :
2014
Journal title :
Nuclear Engineering and Design Eslah
Record number :
1594766
Link To Document :
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