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

Singh, KP and Pandya, SP and Khirwadkar, SS and Patel, Alpesh and Patil, Y and Buch, JJU and Khan, MS and Tripathi, S and Pandya, S and Govindarajan, J and Jaman, PM and Rathore, Devandra and Rangaraj, L and Divakar, C (2011) Pre-qualification of brazed plasma facing components of divertor target elements for ITER like tokamak application. Fusion Engineering and Design, 86. pp. 1741-1744. ISSN 0920-3796

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Abstract

Qualification of tungsten (W) and graphite (C) based brazed plasma facing components (PFCs) is an important R&D area in fusion research. Pre-qualification tests for brazed joints between W–CuCrZr and C–CuCrZr using NDT (IR thermography and ultrasonic test) and thermal fatigue test are attempted. Mockups having good quality brazed joints of W and C based PFCs were identified using NDT. Subsequently, thermal fatigue test was performed on the identified mockups. All brazed tiles ofWbased PFC mockups could withstand thermal fatigue test, however, few tiles of C based PFC mockup were found detached. Thermal analyses of mockups are performed using finite element analysis (ANSYS) software to simulate the thermal hydraulic condition with 10MW/m2 uniform heat flux. Details about experimental and computational work are presented here.

Item Type:	Article
Additional Information:	Copyright for this article belongs to M/s. Elsevier BV
Uncontrolled Keywords:	Plasma facing components (PFCs);Graphite (C);Tungsten (W); NDT;IR thermography;Fatigue test;HHF test
Subjects:	CHEMISTRY AND MATERIALS > Chemistry and Materials (General)
Depositing User:	Ms. Alphones Mary
Date Deposited:	05 Mar 2012 05:23
Last Modified:	05 Mar 2012 05:23
URI:	http://nal-ir.nal.res.in/id/eprint/10366

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