Temperature gradients in the thermally stratified fluid flowing through a pipe may cause undesirable excessive thermal stresses at the pipe wall in the axial, circumferential, and radial directions, which can eventually lead to damages such as deformation, support failure, thermal fatigue, cracking, etc., to the piping systems. Several nuclear power plants have so far experienced such unwelcome mechanical damages to the pressurizer surgeline, feedwater nozzle, high pressure safety injection lines, or residual heat removal lines at a pressurized water reactor (PWR). In this regard, determining with accuracy the transient temperature distributions in the wall of a piping system subjected to internally thermal stratification is the essential prerequisite for the assessment of the structural integrity of such a piping system. In this study, to realistically predict the transient temperature distributions in the wall of an actual PWR pressurizer surgeline with a complex geometry of three-dimensionally bent piping, three-dimensional transient computational fluid dynamics (CFD) calculations involving the conjugate heat transfer analysis are performed for the PWR pressurizer surgeline subjected to either out- or in-surge flows using a commercial CFD code. In addition, the wall temperature distributions obtained by taking into account the existence of wall thickness are compared with those by neglecting it to identify some requirements for a realistic and conservative thermal analysis from a safety viewpoint.
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e-mail: jcjo@kins.re.kr
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April 2010
Research Papers
CFD Analysis of Thermally Stratified Flow and Conjugate Heat Transfer in a PWR Pressurizer Surgeline
Jong Chull Jo,
e-mail: jcjo@kins.re.kr
Jong Chull Jo
Mem. ASME
Korea Institute of Nuclear Safety
, Yusung-gu Daejon 305-338, Korea (Republic)
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Dong Gu Kang
Dong Gu Kang
Korea Institute of Nuclear Safety
, Yusung-gu Daejon 305-338, Korea (Republic)
Search for other works by this author on:
Jong Chull Jo
Mem. ASME
Korea Institute of Nuclear Safety
, Yusung-gu Daejon 305-338, Korea (Republic)e-mail: jcjo@kins.re.kr
Dong Gu Kang
Korea Institute of Nuclear Safety
, Yusung-gu Daejon 305-338, Korea (Republic)J. Pressure Vessel Technol. Apr 2010, 132(2): 021301 (10 pages)
Published Online: January 26, 2010
Article history
Received:
April 2, 2009
Revised:
November 16, 2009
Online:
January 26, 2010
Published:
January 26, 2010
Citation
Jo, J. C., and Kang, D. G. (January 26, 2010). "CFD Analysis of Thermally Stratified Flow and Conjugate Heat Transfer in a PWR Pressurizer Surgeline." ASME. J. Pressure Vessel Technol. April 2010; 132(2): 021301. https://doi.org/10.1115/1.4000727
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