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Lampunio L, Duan Y, Eaton MD. The effect of inlet flow conditions upon thermal mixing and conjugate heat transfer within the wall of a T-Junction. NUCLEAR ENGINEERING AND DESIGN 2021. [DOI: 10.1016/j.nucengdes.2021.111484] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 12/01/2022]
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2
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Effect of temperature difference on the thermal mixing phenomenon in a T-junction under inflow pulsation. NUCLEAR ENGINEERING AND DESIGN 2020. [DOI: 10.1016/j.nucengdes.2020.110611] [Citation(s) in RCA: 6] [Impact Index Per Article: 1.2] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
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3
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Bergagio M, Fan W, Thiele R, Anglart H. Large eddy simulation of thermal mixing with conjugate heat transfer at BWR operating conditions. NUCLEAR ENGINEERING AND DESIGN 2020. [DOI: 10.1016/j.nucengdes.2019.110361] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
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4
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Lu T, Zhang Y, Xu K, Chen Y, Zou J. Investigation on mixing behavior and heat transfer in a horizontally arranged tee pipe under turbulent mixing of hot and cold fluid. ANN NUCL ENERGY 2019. [DOI: 10.1016/j.anucene.2018.11.040] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.7] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
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5
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Timperi A. Comparison of Wall Treatments and Meshes in Large-Eddy Simulations of Mixing Tees. NUCL TECHNOL 2018. [DOI: 10.1080/00295450.2018.1461518] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 10/16/2022]
Affiliation(s)
- Antti Timperi
- VTT Technical Research Centre of Finland Ltd, Nuclear Safety, Kemistintie 3, Espoo, FI-02044, Finland
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Timperi A. Development of a spectrum method for modelling fatigue due to thermal mixing. NUCLEAR ENGINEERING AND DESIGN 2018. [DOI: 10.1016/j.nucengdes.2018.02.039] [Citation(s) in RCA: 2] [Impact Index Per Article: 0.3] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
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Costa Garrido O, El Shawish S, Cizelj L. Assessment of Thermal Fatigue Predictions of Pipes With Spectral Methods. JOURNAL OF NUCLEAR ENGINEERING AND RADIATION SCIENCE 2017. [DOI: 10.1115/1.4036736] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [Abstract] [Track Full Text] [Journal Information] [Subscribe] [Scholar Register] [Indexed: 11/08/2022]
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.
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Affiliation(s)
- Oriol Costa Garrido
- Mem. ASME Reactor Engineering Division, Jožef Stefan Institute, Jamova cesta 39, Ljubljana 1000, Slovenia e-mail:
| | - Samir El Shawish
- Reactor Engineering Division, Jožef Stefan Institute, Jamova cesta 39, Ljubljana 1000, Slovenia e-mail:
| | - Leon Cizelj
- Mem. ASME Reactor Engineering Division, Jožef Stefan Institute, Jamova cesta 39, Ljubljana 1000, Slovenia e-mail:
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Selvam PK, Kulenovic R, Laurien E, Kickhofel J, Prasser HM. Thermal mixing of flows in horizontal T-junctions with low branch velocities. NUCLEAR ENGINEERING AND DESIGN 2017. [DOI: 10.1016/j.nucengdes.2017.06.041] [Citation(s) in RCA: 11] [Impact Index Per Article: 1.4] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/19/2022]
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9
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Cao Q, Li H, Lu D, Chang M. Temperature fluctuation caused by coaxial-jet flow: Experiments on the effect of the velocity ratio R ⩾ 1. NUCLEAR ENGINEERING AND DESIGN 2017. [DOI: 10.1016/j.nucengdes.2017.01.021] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/20/2022]
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10
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Puragliesi R, Zhou L, Zerkak O, Pautz A. Steady-state CFD simulations of an EPR™ reactor pressure vessel: A validation study based on the JULIETTE experiments. NUCLEAR ENGINEERING AND DESIGN 2016. [DOI: 10.1016/j.nucengdes.2015.12.025] [Citation(s) in RCA: 5] [Impact Index Per Article: 0.6] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/28/2022]
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11
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Large eddy simulation studies on the influence of turbulent inlet conditions on the flow behavior in a mixing tee. NUCLEAR ENGINEERING AND DESIGN 2016. [DOI: 10.1016/j.nucengdes.2015.12.001] [Citation(s) in RCA: 10] [Impact Index Per Article: 1.1] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/17/2022]
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12
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CFD based approach for modeling steam–water direct contact condensation in subcooled water flow in a tee junction. PROGRESS IN NUCLEAR ENERGY 2015. [DOI: 10.1016/j.pnucene.2015.09.007] [Citation(s) in RCA: 35] [Impact Index Per Article: 3.5] [Reference Citation Analysis] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/20/2022]
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