NDLI: The Prediction of Global Temperature Profiles in Piping Systems Submitted to Thermal-Stratified Flow From Measured Temperatures on Outside Wall

Content Provider	The American Society of Mechanical Engineers (ASME) Digital Collection
Author	Park, Hong Sun Kang, Sun-Yeh Yoon, Ki-Seok Choi, Taek-Sang Song, Min-Sup Lee, Eui-Suk
Copyright Year	2012
Abstract	Thermal stratification is a common phenomenon in the surge line of Pressurized Water Reactors (PWR). The stratification temperature difference (ΔT) and cyclic behavior severities are the most prevalent during heat-up and cool-down operations of a PWR, when temperature difference between the pressurizer and the hot leg in the Reactor Coolant System (RCS) becomes the largest and inventory fluctuations in RCS are the highest. These behaviors cause cyclic damages and deformations of the pipe. In addition, USNRC recommended integrity evaluations of the piping system submitted to thermal stratified flow in USNRC Bulletin 88–11. In this reason, the importance of monitoring the fatigue induced by the thermal stratified flow in thick-wall pipes rises more and more. To raise the accuracy of solutions for the fatigue damage induced by thermal stratification, the exact global temperature profile is needed to be derived. Many studies have been performed to obtain these profiles. The purpose of this paper is to predict the global temperature profiles in the piping systems submitted to thermal-stratified flow from measured temperatures on the outside wall. It presents both the inverse transfer function method and the numerical-analysis method.
Sponsorship	Pressure Vessels and Piping Division
Starting Page	911
Ending Page	916
Page Count	6
File Format	PDF
ISBN	9780791855027
DOI	10.1115/PVP2012-78738
Volume Number	Volume 3: Design and Analysis
Conference Proceedings	ASME 2012 Pressure Vessels and Piping Conference
Language	English
Publisher Date	2012-07-15
Publisher Place	Toronto, Ontario, Canada
Access Restriction	Subscribed
Subject Keyword	Temperature Deformation Transfer functions Fatigue Temperature profiles Thermal stratification Flow (dynamics) Surges Piping systems Heat Numerical analysis Exterior walls Fluctuations (physics) Nuclear reactor coolants Damage Pressurized water reactors Pipes Fatigue damage Stratified flow
Content Type	Text
Resource Type	Article

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