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2015 | 60 | 2 | 285-288
Tytuł artykułu

R&D on divertor plasma facing components at the Institute for Plasma Research

Treść / Zawartość
Warianty tytułu
Języki publikacji
EN
Abstrakty
EN
This paper is focused on various aspects of the development and testing of water cooled divertor PFCs. Divertor PFCs are mainly designed to absorb the heat and particle fluxes outflowing from the core plasma of fusion devices like ITER. The Divertor and First Wall Technology Development Division at the Institute for Plasma Research (IPR), India, is extensively working on development and testing of divertor plasma facing components (PFCs). Tungsten and graphite macro-brush type test mock-ups were produced using vacuum brazing furnace technique and tungsten monoblock type of test mock-ups were obtained by hot radial pressing (HRP) technique. Heat transfer performance of the developed test mock-ups was tested using high heat flux tests with different heat load conditions as well as the surface temperature monitoring using transient infrared thermography technique. Recently we have established the High Heat Flux Test Facility (HHFTF) at IPR with an electron gun EH300V (M/s Von Ardenne Anlagentechnik GmbH, Germany) having maximum power 200 kW. Two tungsten monoblock type test mock-ups were probed using HHFTF. Both of the test mock-ups successfully sustained 316 thermal cycles during high heat flux (HHF) tests. The test mock-ups were non-destructively tested using infrared thermography before and after the HHF tests. In this note we describe the detailed procedure used for testing macro-brush and monoblock type test mock-ups using in-house transient infrared thermography set-up. An acceptance criteria limit was defined for small scale macro-brush type of mock-ups using DTrefmax value and the surface temperature measured during the HHF tests. It is concluded that the heat transfer behavior of a plasma facing component was checked by the HHF tests followed by transient IR thermography. The acceptance criteria DTrefmax limit for a graphite macro-brush mock-up was found to be ~3°C while for a tungsten macro-brush mock-up it was ~5°C.
Wydawca

Czasopismo
Rocznik
Tom
60
Numer
2
Strony
285-288
Opis fizyczny
Daty
wydano
2015-06-01
otrzymano
2014-06-30
zaakceptowano
2015-01-07
online
2015-06-22
Twórcy
  • Divertor and First Wall Technology Development Division, Institute for Plasma Research, Bhat, Gandhinagar-382428, Gujarat, India, Tel.: +91 79 2396 2037, ypatil@ipr.res.in
  • Divertor and First Wall Technology Development Division, Institute for Plasma Research, Bhat, Gandhinagar-382428, Gujarat, India, Tel.: +91 79 2396 2037
  • Divertor and First Wall Technology Development Division, Institute for Plasma Research, Bhat, Gandhinagar-382428, Gujarat, India, Tel.: +91 79 2396 2037
  • Divertor and First Wall Technology Development Division, Institute for Plasma Research, Bhat, Gandhinagar-382428, Gujarat, India, Tel.: +91 79 2396 2037
autor
  • Divertor and First Wall Technology Development Division, Institute for Plasma Research, Bhat, Gandhinagar-382428, Gujarat, India, Tel.: +91 79 2396 2037
autor
  • Divertor and First Wall Technology Development Division, Institute for Plasma Research, Bhat, Gandhinagar-382428, Gujarat, India, Tel.: +91 79 2396 2037
autor
  • Divertor and First Wall Technology Development Division, Institute for Plasma Research, Bhat, Gandhinagar-382428, Gujarat, India, Tel.: +91 79 2396 2037
Bibliografia
  • 1. Merola, M., Danner, W., Pick, M., & the UE ITER Participating Team. (2005). EU R&D on divertor components. Fusion Eng. Des., 75/79, 325–331.
  • 2. Linke, J. (2006). Plasma facing materials and components for future fusion devices – development, characterization and performance under fusion specific loading conditions. Phys. Scripta, T123, 45–53. DOI: 10.1088/0031-8949/2006/T123/006.[Crossref]
  • 3. Merola, M., Palmer, J., & the UE ITER Participating Team. (2006). EU acitivities in preparation of the procurement of the ITER divertor. Fusion Eng. Des., 81, 105–112.[WoS]
  • 4. Durocher, A., Vignal, N., Escourbiac, F., Farjon, J. L., Schlosser, J., & Cismondi, F. (2005). Development of an original active thermography method adapted to ITER plasma facing components control. Fusion Eng. Des., 75/79, 401–405.
  • 5. Khirwadkar, S. S., Singh, K. P., Patil, Y., Khan, M. S., Buch, J. J., Patel, A., Tripathi, S., Jaman, P. M., Rangaraj, L., & Divakar, C. (2011). Fabrication and characterization of tungsten and graphite based PFC for divertor target elements of ITER like tokamak application. Fusion Eng. Des., 86, 1736–1740.[WoS]
  • 6. Patil, Y., Khirwadkar, S. S., Krishnan, D., Patel, A., Tripathi, S., Singh, K. P., & Belsare, S. M. (2013). High heat flux performance of brazed tungsten macro-brush test mock-up for divertors. J. Nucl. Mater., 437, 326–331.[WoS]
  • 7. Singh, K. P., Pandya, S. P., Khirwadkar, S. S., Patel, A., Patil, Y., Buch, J. J. U., Khan, M. S., Tripathi, S., Pandya, S., Govindrajan, J., Jaman, P. M., & Rathore, D. (2011). Pre-qualification of brazed plasma facing components of divertor target elements for ITER like tokamak application. Fusion Eng. Des., 86, 1741–1744.[WoS]
  • 8. Patil, Y., Khirwadkar, S. S., Belsare, S. M., Rajamannar, Swamy, Khan, M. S., Tripathi, S., Bhope, K., Krishnan, D., Mokaria, P., Patel, N., Antwala, I., Galodiya, K., Mehta, M., & Patel, T. (2015). Performance of straight tungsten mono-block test mock-ups using new high heat flux test facility at IPR. Fusion Eng. Des., 95, 84–90.
  • 9. Mitteau, R., & et al. (1996). Non destructive testing of actively cooled plasma facing components by means of thermal transient exciation and infrared imaging. In Proceedings of 19th Symposium on Fusion Technology (SOFT), September 16–20, 1996 (pp. 443–446). Lisbonne.
  • 10. Durocher, A., Escourbiac, F., Richou, M., Vignal, N., Merola, M., Riccardi, B., Cantone, V., & Constans, S. (2009). Infrared thermography inspection of the ITER vertical target qualification prototypes manufactured by European industry using SATIR. Fusion Eng. Des., 84, 314–318.[WoS]
Typ dokumentu
Bibliografia
Identyfikatory
Identyfikator YADDA
bwmeta1.element.-psjd-doi-10_1515_nuka-2015-0053
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