Pre-qualification of brazed plasma facing components of divertor target elements for ITER like tokamak application

Singh, K. P.; Pandya, Santosh P.; Khirwadkar, S.S.; Patel, Ankit R.; Patil, Yashashri; Buch, J.; Khan, Mohammad Shoaib; Tripathi, Sudhir; Pandya, Shwetang N.; Govindrajan, J.; Jaman, PM; Rathore, Devendra; Rangaraj, Lingappa; Divakar, C

doi:10.1016/j.fusengdes.2011.01.137

Cited by 10 publications

(4 citation statements)

References 13 publications

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“…Prior to micro-structural examination and destructive testing (mechanical strength testing) of the joints, the brazed mockups were characterized by nondestructive testing techniques such as ultrasonic testing (UT) and IR-Thermography [13].…”

Section: Methodsmentioning

confidence: 99%

Fabrication and characterization of tungsten and graphite based PFC for divertor target elements of ITER like tokamak application

Khirwadkar

Singh

Patil

et al. 2011

Fusion Engineering and Design

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Section: Methodsmentioning

confidence: 99%

Fabrication and characterization of tungsten and graphite based PFC for divertor target elements of ITER like tokamak application

Khirwadkar

Singh

Patil

et al. 2011

Fusion Engineering and Design

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“…Research on first wall and divertor development activities at IPR involves materials development and processing studies of W, W-based alloys, CFC, CuCrZr alloy, their joining studies and the performance tests such as high heat flux testing (Khirwadkar et al, 2011;Singh et al, 2011;Patil et al, 2013). Reduced activation ferritic martensitic steels have been developed for the Indian TBM programme as per the composition specified in Table 5 (Saroja et al, 2011).…”

Section: Status Of Materials Development In Indiamentioning

confidence: 99%

Materials Research and Development Opportunities in Reactors Fusion

Mukherjee¹

2015

Proceedings of the Indian National Science Academy

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“…Two types of tungsten monoblock type test mock-ups were tested using HHFTF. Both of the test mock--ups successfully sustained 316 thermal cycles with [7,8]. Figure 3 shows the thermal cyclic performance of graphite macro-brush type of test mock-up during HHF tests with absorbed heat fl ux 7.2 MW/m 2 corresponding incident heat flux 10 MW/m 2 .…”

Section: High Heat Flux Test Facility and Hhf Testsmentioning

confidence: 99%

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

et al. 2015

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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.

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Pre-qualification of brazed plasma facing components of divertor target elements for ITER like tokamak application

Cited by 10 publications

References 13 publications

Fabrication and characterization of tungsten and graphite based PFC for divertor target elements of ITER like tokamak application

Fabrication and characterization of tungsten and graphite based PFC for divertor target elements of ITER like tokamak application

Materials Research and Development Opportunities in Reactors Fusion

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

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