contributor author | Costa Garrido, Oriol | |
contributor author | El Shawish, Samir | |
contributor author | Cizelj, Leon | |
date accessioned | 2017-11-25T07:18:43Z | |
date available | 2017-11-25T07:18:43Z | |
date copyright | 2017/31/7 | |
date issued | 2017 | |
identifier issn | 2332-8983 | |
identifier other | ners_003_04_041001.pdf | |
identifier uri | http://138.201.223.254:8080/yetl1/handle/yetl/4235349 | |
description abstract | Large sets of fluid temperature histories and a recently proposed thermal fatigue assessment procedure are employed in this paper to deliver more accurate statistics of predicted lives of pipes and their uncertainties under turbulent fluid mixing circumstances. The wide variety of synthetic fluid temperatures, generated with an improved spectral method, results in a set of estimated distributions of fatigue lives through linear one-dimensional (1D) heat diffusion, thermal stress estimates, and fatigue assessment codified rules. The results of the fatigue analysis indicate that, in order to avoid the inherent uncertainties due to comparatively short fluid temperature histories to the estimated fatigue lives, a conservative safe design against thermal fatigue could be attempted with the lower bounds of the predicted life distributions, such as the 5% probability life (5% of samples fail). The impact of the convection heat transfer coefficient on the predictions is also studied in a sensitivity analysis. This represents a detailed attempt to correlate the uncertainties in the physical fluid mixing conditions and heat transfer to the estimated fatigue life using spectral methods. | |
publisher | The American Society of Mechanical Engineers (ASME) | |
title | Assessment of Thermal Fatigue Predictions of Pipes With Spectral Methods | |
type | Journal Paper | |
journal volume | 3 | |
journal issue | 4 | |
journal title | Journal of Nuclear Engineering and Radiation Science | |
identifier doi | 10.1115/1.4036736 | |
journal fristpage | 41001 | |
journal lastpage | 041001-8 | |
tree | Journal of Nuclear Engineering and Radiation Science:;2017:;volume( 003 ):;issue: 004 | |
contenttype | Fulltext | |