Nuclear Engineering and Design 239 (2009) 833–839
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Nuclear Engineering and Design
journal homepage: www.elsevier.com/locate/nucengdes
Numerical analysis of thermal striping induced high cycle thermal
fatigue in a mixing tee
Jeong Ik Lee, Lin-wen Hu
∗
, Pradip Saha, Mujid S. Kazimi
Center for Advanced Nuclear Energy Systems, Massachusetts Institute of Technology, 77 Massachusetts Avenue, Cambridge, MA 02139, USA
article info
Article history:
Received 20 November 2007
Received in revised form 3 June 2008
Accepted 18 June 2008
abstract
Thermal striping, characterized by turbulent mixing of two flow streams of different temperatures that
result in temperature fluctuations of coolant near the pipe wall, is one of the main causes of thermal
fatigue failure. Coolant temperature oscillations due to thermal striping are on the order of several Hz.
Thermal striping high-cycle thermal fatigue that occurs at tee junctions is one of the topics that should
be addressed for the life management of light water reactor (LWR) piping systems. This study focuses on
numerical analyses of the temperature fluctuations and structural response of coolant piping at a mixing
tee. The coolant temperature fluctuations are obtained from Large Eddy Simulations that are validated by
experimental data. For the thermal stress fatigue analysis, a model is developed to identify the relative
importance of various parameters affecting fatigue-cracking failure. This study shows that the temperature
difference between the hot and cold fluids of a tee junction and the enhanced heat transfer coefficient
due to turbulent mixing are the dominant factors of thermal fatigue failure of a tee junction.
© 2008 Elsevier B.V. All rights reserved.
1. Introduction
Prediction of high cycle fatigue in mixing tees is a challenging
subject for life management of nuclear power reactor piping sys-
tems. Thermal striping is one of the phenomena that resulted in
thermal fatigue failure, and is characterized by turbulent mixing of
hot and cold flow streams that result in temperature fluctuations of
the coolant near a piping wall. The coolant temperature fluctuations
may cause cyclical thermal stresses and subsequent fatigue crack-
ing of the pipe wall. Coolant temperature oscillations due to thermal
striping are of relatively high frequencies, reported previously to
be on the order of several Hz (Wakamatsu et al., 1995).Studies of
thermal striping were initially carried out for liquid–metal-cooled
fast breeder reactor (LMFBR) in 1980s because of the high thermal
conductivity of the liquid metal coolant (Muramatsu and Ninikata,
1996). Areas susceptible to thermal striping include components
in the core outlet region, such as core upper plenum, flow guide
tube, and control rod upper guide tubes. Outside the core region,
components where hot and cold streams come in contact, such
as tee junctions, elbows, and leakage from valves, may also be
affected. The issue of thermal striping shifted to light water reac-
tors (LWRs) after several incidents of piping failure at some nuclear
power plants (Kim et al., 1993; Fukuka et al., 2003; Claude, 2003).
∗
Corresponding author. Tel.: +1 617 258 5860; fax: +1 617 253 7300.
E-mail address: lwhu@mit.edu (L.-w. Hu).
The piping systems that are most susceptible to thermal striping
fatigue cracking are mixing tees of the residual heat removal (RHR)
systems in both BWR and PWR.
Evaluation of thermal striping can be performed by mock-
up experiments or three-dimensional, unsteady computational
fluid dynamics (CFD) simulations. The primary goal is to iden-
tify the temperature fluctuation magnitude and frequencies. The
local thermal stresses of the pipe are proportional to the temper-
ature oscillations in the pipe wall, normally a fraction of those
in the coolant. The accumulative thermal stress cycles are then
applied for stress and strain analysis. In experiments where coolant
and pipe wall temperatures were measured, both frequencies
and magnitudes of temperature fluctuations can be obtained at
selected locations in the pipes. Thermal striping was modeled
previously using large eddy simulation (LES) and direct numer-
ical simulation (DNS) (Muramatsu and Ninikata, 1996; Roubin,
1998). However, these studies were conducted for only a small
control volume around the mixing zone due to computing power
constraints. Therefore, careful selection of the subdomain and
associated boundary conditions play an important role in such
numerical analysis.
Our benchmark study, discussed in this paper, demonstrates
that LES can predict accurately the temperature fluctuations asso-
ciated with thermal striping. A fatigue cracking analysis was
conducted using the thermal stress and stress intensity factor (SIF)
for comparison of important variables. The objective of this study
is to identify the effects of these variables through sensitivity anal-
0029-5493/$ – see front matter © 2008 Elsevier B.V. All rights reserved.
doi:10.1016/j.nucengdes.2008.06.014