A5005547642- Fusion materials and technologies
- Magnetic confinement fusion research
- Superconducting Materials and Applications
- Nuclear Materials and Properties
- Advanced materials and composites
- Laser-Plasma Interactions and Diagnostics
- Nuclear Engineering Thermal-Hydraulics
- Geophysics and Sensor Technology
- Particle accelerators and beam dynamics
- Heat Transfer and Boiling Studies
- Advanced Sensor Technologies Research
- Gyrotron and Vacuum Electronics Research
- Fatigue and fracture mechanics
- Cyclone Separators and Fluid Dynamics
- Magneto-Optical Properties and Applications
- Nuclear reactor physics and engineering
- Powder Metallurgy Techniques and Materials
- Fire effects on concrete materials
- Structural Behavior of Reinforced Concrete
- Nuclear Physics and Applications
- Metal Alloys Wear and Properties
- Induction Heating and Inverter Technology
- Ion-surface interactions and analysis
- Rocket and propulsion systems research
Institute for Plasma Research
2015-2025
The High Heat Flux Test Facility (HHFTF) was designed and established recently at Institute for Plasma Research (IPR) in India testing heat removal capability operational life time of plasma facing materials components the ITER-like tokamak. HHFTF is equipped with various diagnostics such as IR cameras IR-pyrometers surface temperature measurements, coolant water calorimetry absorbed power measurements thermocouples bulk measurements. capable simulating steady state load several MW m−2 well...
The WEST tokamak consists of a major upgrade the superconducting medium size Tore Supra aiming at testing ITER divertor components. Such modification has required rebuilding full set magnetic diagnostics. project was started in 2013 and completed 2016. diagnostic 469 sensors (421 pick-up coils, 36 flux loops, 12 Rogowski coils) installed vacuum vessel. New analog integrators have been developed order to obtain field from raw signal sensors. During startup phase WEST, plasma currents few kilo...
Abstract This paper is focused on various aspects of the development and testing water cooled divertor PFCs. Divertor PFCs are mainly designed to absorb heat particle fluxes outflowing from core plasma fusion devices like ITER. The First Wall Technology Development Division at Institute for Plasma Research (IPR), India, extensively working facing components (PFCs). Tungsten graphite macro-brush type test mock-ups were produced using vacuum brazing furnace technique tungsten monoblock...
High-power tests on chemical vapor deposited (CVD) diamond window are carried out using 82.6-GHz Gyrotron. To test CVD with calorimetric dummy load, a matching optic unit is designed and fabricated special profiled mirrors. The mirrors by Gycom Russia mirror box assembly at Institute for Plasma Research. cooled water. consists of four arc detectors the protection window. connected to load this box. alignment done during testing in pulsed condition. After achieving desired Gaussian pattern...
The aim of the work is to develop fabrication technology a small curved tungsten (W) macro-brush–type geometry using vacuum brazing technique. Taking design concept ITER divertor dome, present mock-up has scaled down more than ten times in size. A feasibility study was done, and special fixture for profile were carried out. technique used joining tiles CuCrZr block (heat sink) silver-free alloy (NiCuMn-37) with specially designed custom-made (Type 304 stainless steel). Nondestructive...
During operation of an ITER-like plasma fusion device, Plasma Facing Components (PFCs) a divertor are subjected to steady-state and transient heat loads up 20 MW/m2. At High Heat Flux Test Facility (HHFTF) at Institute for Research, PFCs such flux scenarios using 200 kW electron beam (EB). A distribution on is significantly influenced by the EB profile scanning technique. novel dual-technique approach used measure cross-sectional profiles in HHFTF. single setup designed, fabricated,...
The back plate is an important component of the ion source because its multiple roles including heat load removal during beam operation. main components are (1) a Type 304L stainless steel (SS304L) magnet positioning that holds samarium cobalt permanent magnets required for confinement plasma, (2) oxygen-free electronic copper cooling with 35 inner and 8 outer channel grooves (each which 4 × 1.8 mm2) vacuum brazed SS304L plate, (3) cover plate. In this paper, successfully fabricated, high...
High power tests on CVD diamond window are carried out using 82.6GHz Gyrotron. In order to test with calorimetric dummy load, a matching optic unit is designed and fabricated special profiled mirrors. The mirrors by M/s. Gycom Russia mirror box assembly at IPR. cooled water. consists of four arc detectors for the protection window. connected load this box. alignment done during testing in pulsed condition. After achieving desired Gaussian pattern exit box, system CW test. tested up 60 kW 10 minutes.
High heat flux test facility (HHFTF) at IPR is used for testing thermal performance of plasma facing materials or components. It consists various subsystems like vacuum system, high power electron beam diagnostic and calibration data acquisition control system pressure temperature water circulation system. Vacuum large D-shaped chamber, target handling pumping systems support structure. The net volume chamber 5 m3 was maintained the base order 10-6 mbar operation gun with minimum diameter...
Institute for Plasma Research (IPR) is involved in development of various technologies fabrication & testing/qualification Tungsten (W) based plasma facing components (PFCs) ITER-like applications. As a part these activities, small scale W/Cu/CuCrZr mono-block test mock-up prepared by using vacuum brazing process. Further, thermal fatigue testing this performed High Heat Flux Test Facility (HHFTF) at IPR under absorbed heat flux ~9.5 MW/m2 1200 cycles. Thermal hydraulic analysis and...
The Institute for Plasma Research (IPR) is involved in the development of various technologies fabrication and testing/qualification tungsten (W)–based plasma-facing components ITER-like applications. As a part these activities, small-scale W/Cu/CuCrZr monoblock test mock-up prepared by using vacuum brazing process. Further, thermal fatigue testing this performed High Heat Flux Test Facility at IPR under an absorbed heat flux ~9.5 MW/m2 1200 cycles. Thermal-hydraulic analysis computational...