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Apicella ML, Buscarino A, Corradino C, Fortuna L, Mazzitelli G, Xibilia MG. Model identification of the temperature over the FTU cooled liquid lithium (CLL) limiter surface. Fusion Engineering and Design 2017. [DOI: 10.1016/j.fusengdes.2017.05.066] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/19/2022]
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Pandya SP, Pandya SN, Patil YV, Krishnan DS, Murugesan M, Sharath D, Singh KP, Khan MS, Arafat M, Biju N, Khirwadkar SS, Govidarajan J, Venkatraman B, Balasubramaniam K. A comparison between finite element modeling and various thermographic non-destructive testing techniques for the quantification of the thermal integrity of macro-brush plasma facing components used in a tokamak. Rev Sci Instrum 2016; 87:024901. [PMID: 26931878 DOI: 10.1063/1.4940728] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [What about the content of this article? (0)] [Affiliation(s)] [Abstract] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 06/05/2023]
Abstract
The plasma facing components (PFCs) inside a tokamak are typically exposed to extremely high heat flux of the order of MW/m(2). The brazing quality between the plasma facing materials (PFMs) and the heat sink will determine the structural integrity and hence the effective service life of these PFCs. Suitable non-destructive testing (NDT) techniques for the pre-qualification of these components are thus essential to evaluate their structural integrity at various stages of their service life. Macro-brush type mockups of prototype PFCs with graphite as PFM have been inspected for their brazing quality using different active Infrared (IR)-thermographic NDT techniques. The results obtained from these techniques are compared and discussed. The brazing quality was quantified by establishing a comparison between the experimental results and the results from Finite Element Analysis (FEA). The percentage of contact between the PFM and the substrate was varied in FEA. FEA results when compared with experiments shows that tiles have different amounts of contact with the substrate ranging between 10% and 80%.
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Affiliation(s)
- Santosh P Pandya
- Institute for Plasma Research, Village Bhat, Indira Bridge, Gandhinagar 382 428, India
| | - Shwetang N Pandya
- Institute for Plasma Research, Village Bhat, Indira Bridge, Gandhinagar 382 428, India
| | - Yashashri V Patil
- Institute for Plasma Research, Village Bhat, Indira Bridge, Gandhinagar 382 428, India
| | - Deepu S Krishnan
- Institute for Plasma Research, Village Bhat, Indira Bridge, Gandhinagar 382 428, India
| | - Menaka Murugesan
- Indira Gandhi Centre for Atomic Research, Kalpakkam 603 102, India
| | - D Sharath
- Indira Gandhi Centre for Atomic Research, Kalpakkam 603 102, India
| | - K Premjit Singh
- Institute for Plasma Research, Village Bhat, Indira Bridge, Gandhinagar 382 428, India
| | - Md Shoaib Khan
- Institute for Plasma Research, Village Bhat, Indira Bridge, Gandhinagar 382 428, India
| | - M Arafat
- Centre for NDE, Indian Institute of Technology, Chennai 600 036, India
| | - N Biju
- School of Engineering, Cochin University of Science and Technology, Cochin 682 022, India
| | - Samir S Khirwadkar
- Institute for Plasma Research, Village Bhat, Indira Bridge, Gandhinagar 382 428, India
| | | | - B Venkatraman
- Indira Gandhi Centre for Atomic Research, Kalpakkam 603 102, India
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Singh K, Pandya SP, Khirwadkar S, Patel A, Patil Y, Buch J, Khan M, Tripathi S, Pandya S, Govindrajan J, Jaman P, Rathore D, Rangaraj L, Divakar C. Pre-qualification of brazed plasma facing components of divertor target elements for ITER like tokamak application. Fusion Engineering and Design 2011. [DOI: 10.1016/j.fusengdes.2011.01.137] [Citation(s) in RCA: 7] [Impact Index Per Article: 0.5] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/29/2022]
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Tahiliani K, Pandya SP, Pandya S, Jha R, Govindarajan J. Nondestructive test of brazed cooling tubes of prototype bolometer camera housing using active infrared thermography. Rev Sci Instrum 2011; 82:014901. [PMID: 21280850 DOI: 10.1063/1.3506396] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [What about the content of this article? (0)] [Affiliation(s)] [Abstract] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 05/30/2023]
Abstract
The active infrared thermography technique is used for assessing the brazing quality of an actively cooled bolometer camera housing developed for steady state superconducting tokamak. The housing is a circular pipe, which has circular tubes vacuum brazed on the periphery. A unique method was adopted to monitor the temperature distribution on the internal surface of the pipe. A stainless steel mirror was placed inside the pipe and the reflected IR radiations were viewed using an IR camera. The heat stimulus was given by passing hot water through the tubes and the temperature distribution was monitored during the transient phase. The thermographs showed a significant nonuniformity in the brazing with a contact area of around 51%. The thermography results were compared with the x-ray radiographs and a good match between the two was observed. Benefits of thermography over x-ray radiography testing are emphasized.
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Seki Y, Ezato K, Suzuki S, Yokoyama K, Enoeda M, Mori S. Non-destructive examination with infrared thermography system for ITER divertor components. Fusion Engineering and Design 2010; 85:1451-4. [DOI: 10.1016/j.fusengdes.2010.04.010] [Citation(s) in RCA: 16] [Impact Index Per Article: 1.1] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/24/2022]
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Guigon R, Le Niliot C, Missirlian M, Courtois X, Cismondi F. Innovative image processing techniques applied to the thermographic inspection of PFC with SATIR facility. Fusion Engineering and Design 2009. [DOI: 10.1016/j.fusengdes.2008.11.034] [Citation(s) in RCA: 1] [Impact Index Per Article: 0.1] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/21/2022]
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Missirlian M, Boscary J, Guigon R, Schlosser J, Durocher A, Greuner H. Upgraded acceptance criteria from transient thermography control for the W7-X divertor target elements. Fusion Engineering and Design 2009. [DOI: 10.1016/j.fusengdes.2008.12.080] [Citation(s) in RCA: 0] [Impact Index Per Article: 0] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/21/2022]
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Durocher A, Moysan J, Escourbiac F, Missirlian M, Vignal N, Boscary J. Infrared images data merging for plasma-facing component inspection. Fusion Engineering and Design 2007. [DOI: 10.1016/j.fusengdes.2007.07.040] [Citation(s) in RCA: 4] [Impact Index Per Article: 0.2] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/16/2022]
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Escourbiac F, Durocher A, Grosman A, Cismondi F, Courtois X, Farjon J, Schlosser J, Merola M, Tivey R. Qualification, commissioning and in situ monitoring of high heat flux plasma facing components. Fusion Engineering and Design 2007; 82:1730-8. [DOI: 10.1016/j.fusengdes.2007.06.004] [Citation(s) in RCA: 7] [Impact Index Per Article: 0.4] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 11/22/2022]
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Boscary J, Greuner H, Mendelevitch B, Schedler B, Scheiber K, Schlosser J, Streibl B. Applied technologies and inspections for the W7-X pre-series target elements. Fusion Engineering and Design 2005. [DOI: 10.1016/j.fusengdes.2005.06.101] [Citation(s) in RCA: 22] [Impact Index Per Article: 1.2] [Reference Citation Analysis] [What about the content of this article? (0)] [Track Full Text] [Subscribe] [Scholar Register] [Indexed: 10/25/2022]
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