scholarly journals Establishment of a JSME Code for the Evaluation of High-Cycle Thermal Fatigue for Thermal Striping in Mixing Tees with Hot and Cold Water : The Outlines of Series Presentations and the Proposed JSME Code

2002 ◽  
Vol 2002 (0) ◽  
pp. 477-478
Author(s):  
Shoichi MORIYA ◽  
Toshihiko FUKUDA ◽  
Yasuhiko MINAMI ◽  
Kenji OGURA ◽  
Kouji SHINA ◽  
...  
Author(s):  
Mohammed Hasan ◽  
Debashis Basu ◽  
Kaushik Das

Thermal striping generally is recognized as a significant long-term degradation mechanism in the primary cooling water circuit of nuclear power plants (NPPs). This phenomenon occurs by mixing of hot and cold water streams in the primary coolant loop. Depending on the flow configuration, the turbulent mixing process can lead to thermal striping, temperature fluctuations in the T-junction region, thermal fatigue, and crack generation in the associated structure. The objective of this study is to provide an in-depth look into the underlying physics for thermal fatigue to determine appropriate screening criteria and risk significance for the regulatory safety evaluation process. In addition, the structure of turbulence in the T-junction also is investigated. The computational method comprised of Large Eddy Simulation (LES) modeling to simulate turbulence and Proper Orthogonal Decomposition (POD) analysis to capture the coherent structures and turbulence scales. In addition, Conjugate Heat Transfer (CHT) analyses have been performed to predict the thermal field and temperature distribution in the solid piping material of the T-junction. Finally, the corresponding thermal stress in the solid pipe is estimated based on a simplified one-dimensional model to assess the thermal-structure degradation.


Author(s):  
Masaaki Tanaka ◽  
Yasuhiro Miyake

Thermal striping phenomena caused by mixing of fluids at different temperature is one of the most important issues in design of Fast Breeder Reactors (FBRs), because it may cause high-cycle thermal fatigue in structure and affect the structural integrity. A numerical simulation code MUGTHES has been developed to investigate thermal striping phenomena and to estimate high cycle thermal fatigue in FBRs. In this study, numerical simulation for the WATLON experiment which was the water experiment of a T-junction piping system (T-pipe) conducted in JAEA was carried out to validate the MUGTHES and to investigate the relation between the mechanism of temperature fluctuation generation and the unsteady motion of large eddy structures. In the numerical simulation, the large eddy simulation (LES) approach with standard Smagorinsky model was employed as eddy viscosity model to simulate large-scale eddy motion in the T-pipe. The mesh as the same with the previous study as reference, the finer mesh and the coarser mesh arrangements were employed to estimate the Grid Convergence Index (GCI) for uncertainty quantification in the validation process. The modified method of the GCI estimation based on the least squire version could successfully quantify uncertainty. Through the numerical simulations, it was indicated that the fine mesh arrangement could improve the temperature distribution in the wake. It could be found that the thermal mixing phenomena in the T-pipe were caused by the mutual interaction of the necklace-shaped vortex around the wake from in the front of the branch jet, the horseshoe-shaped vortex and the Karman’s vortex motions in the wake.


2009 ◽  
Vol 239 (5) ◽  
pp. 833-839 ◽  
Author(s):  
Jeong Ik Lee ◽  
Lin-wen Hu ◽  
Pradip Saha ◽  
Mujid S. Kazimi

2013 ◽  
Vol 27 (10) ◽  
pp. 3087-3095 ◽  
Author(s):  
Sun-Hye Kim ◽  
Nam-Su Huh ◽  
Moon-Ki Kim ◽  
Dae-Geun Cho ◽  
Young-Hwan Choi ◽  
...  

Author(s):  
J. M. Stephan ◽  
F. Curtit

In 1998, a leak occurred in the main mixing zone of the residual heat removal systems (RHR) of the EDF CIVAUX nuclear plant unit 1. The crack is attributed to high-cycle thermal fatigue due to the fluid thermal turbulences. An research and development (R&D) program is now being conducted at EDF to understand the incident and to assess the risks of cracks in other mixing zones. This program includes thermal-hydraulic tests on mock-ups and their numerical interpretation, material testing in high-cycle fatigue, structure tests on mock-ups submitted to high-cycle thermal stresses and their interpretations, and developments in non destructive evaluations in the presence of crazing zones (thermal striping). After a brief presentation of the R&D program, the paper presents a new high-cycle thermal fatigue bench test, named INTHERPOL, for pipe structures. The thermal cycles consist of periodic controlled cold shocks by water sprays and hot shocks by infrared radiations on the inner surface of part of the structure. The structure under test, the water spray devices and infrared modules are inserted into a tank to allow constant control of the environment. The types of pipe structures tested include plain or welded structures and various industrial surface finishes. The first tests results and their numerical interpretations are presented.


Author(s):  
Kohei Soda ◽  
Takato Mizutani ◽  
Naoto Kasahara

In nuclear power plants, high cycle thermal fatigue induced by temperature fluctuation of the coolant is one of frequent failure modes. To ensure the safety of nuclear power plant systems, it is important to prevent thermal fatigue failure. Typical causes of high cycle thermal fatigue are thermal striping at Tee-junction and thermal stratification oscillation. In order to evaluate thermal stress caused by thermal striping, a frequency response function has been developed. This function was derived from a heat transfer and thermal elastic theories, and can adequately evaluate thermal stress induced by temperature gradient into wall-thickness direction. However, this theoretical method cannot adequately evaluate thermal stress by thermal stratification oscillation, because this phenomenon has the fluid temperature distribution gradient along axial direction. To investigate the mechanism of thermal stress generated by oscillation of thermal stratification, two types of models were studied. In the first type, fluid temperature oscillates with sinusoidal history at the same location, and in the second one, the boundary layer of hot and cold fluid temperature moves with sinusoidal velocity. Through clarification of the stress generation mechanism, the frequency response function was improved to evaluate stress by the thermal stratification oscillation. Applicability of this function was verified through agreement with finite element simulations.


Author(s):  
Simon Kuhn ◽  
Bojan Nicˇeno ◽  
Horst-Michael Prasser

Thermal fatigue is a relevant problem in the context of life-time extension of nuclear power plants (NPP). In many piping systems in NPPs hot and cold water is mixed, which leads to high temperature fluctuations in the region close to the solid wall and resulting thermal loads on the pipe walls that can cause fatigue. One of the relevant geometric test cases for thermal fatigue is the mixing in T-junctions. In this study we apply large–eddy simulations (LES) to the mixing of hot and cold water in a T-junction. We perform a set of simulations by using different formulations of the LES subgrid scale model, i.e. standard Smagorinsky and dynamic procedure, to identify the influence of the modelled subgrid scales on the simulation results. The results exhibit a large difference between the models, which is caused by the use of turbulent viscosity wall–damping functions when applying the standard model.


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