CFD Analysis of Thermally Stratified Flow and Conjugate Heat Transfer in a PWR Pressurizer Surgeline

Author:

Jo Jong Chull12,Kang Dong Gu2

Affiliation:

1. Mem. ASME

2. Korea Institute of Nuclear Safety, Yusung-gu Daejon 305-338, Korea (Republic)

Abstract

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.

Publisher

ASME International

Subject

Mechanical Engineering,Mechanics of Materials,Safety, Risk, Reliability and Quality

Reference18 articles.

1. USNRC, 1979, “Cracking in Feedwater System Piping,” NRC Bulletin No. 79-13.

2. USNRC, 1988, “Thermal Stresses in Piping Connected to Reactor Coolant Systems,” NRC Bulletin No. 88-08.

3. USNRC, 1988, “Pressurizer Surgeline Thermal Stratification,” NRC Bulletin No. 88-11.

4. USNRC, 1989, “Review of Industry Efforts to Manage Pressurized Water Reactor Feedwater Nozzle, Piping, and Feedering Cracking and Wall Thinning,” Report No. NUREG/CR-6456.

5. Results of Thermal Stratification Tests in a Horizontal Pipe Line at the HDR-Facility;Talja;Nucl. Eng. Des.

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