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The ECRH system on Aditya-U The 42GHz-500kW ECRH system Electron Cyclotron Resonance Heating (ECRH) system helps tokamak for reliable plasma start-up, heating, current drive and instability control. The ECRH system consists of high power microwave source (Gyrotron), corrugated waveguide...

Proposed LI-VISTA Test Facility. Beam tube is one of the important part of the entire vacuum system. It is a cylindrical structure having 4 km length in each perpendicular direction. The beam tube is kept in ultra-high vacuum so that scattering of laser beam is minimized within the...

CIMPLE -PSI Device , Indias first linear magnetized plasma system for fusion related plasma surface interaction studies. //////////////////////////////// Cryocooler based Helium Circulation System at 55K was successfully installed at IPR. The main purpose of this system is to cool the High...

Diagnostic Shield Module (DSM) for the Diagnostic ports of ITER tokamak developed in India. Design of DSM Final product .This is used in DSM of ITER, DSM is for Shielding against the Neutrons produced by nuclear reaction. these are based on hot pressed boron carbide blocks/pellets...

ITER 4.8 KM OF CRYOLINES PASS LEAK TEST The cryoline network is built out of individual spools that measure up to 10 metres in length and range from 25 to 1000 millimetres in diameter. A section of cryoline can host up to six or seven "process pipes," each devoted to a specific fluid, flow...

After 25 years of successful operation of ADITYA tokamak (~ 30,000 discharges) in a circular poloidal ring limiter configuration, it has been upgraded to a tokamak named ADITYA Upgrade (ADITYA-U) to realize the shaped-plasma operations in an open diverter configurations. The upgradation was...

ADITYA-U resumed operations from 24 November, 2020 and continued till 18 th December, 2020. Almost 227 discharges were obtained with varied toroidal magnetic field (B) from 0.9 Tesla to 1.07 Tesla. The extensive wall conditioning with Hydrogen GDC as well as combination of Argon + Hydrogen GDC...

Startup plans nuclear fusion plant in India. Akash Singh, an Indian-origin entrepreneur based out of Silicon Valley, is all set to venture into nuclear fusion by early next year. Singh is working on 'Project Sanlayan', which is supported by a team of international investors. This was revealed...

ADITYA U Vaccum Vessel ECRH System in ADITYA LH Grill Anteena Toroidal Field Coils Toroidal Belt Limiter Vacuum Vessel ADITYA U Vacuum vessel Support Structures

42 GHz Gyrotron System ADITYA Dismantled at 2015. very old pics of ADITYA TOKOMAK ADITYA Poloidal Limiters inside the vacuum Vessel ADITYA Vacuum vessel at L&T facility Mumbai an old pic ADITYA Upgraded Upgraded vaccum vessel Godrej

Quadrapole magnets 7 Nos Dipole Corrector 60 degree bending magnet these magnet are for Delhi Light Source 42 GHz, 200 kW Gyrotron for Indian TOKAMAK system

MEBT Quadrupole Triplets & Doublets ( Magnets ) Medium Energy Beam transport line (MEBT) Doublets for LB-HB 650 MHz section of PIP-II

Permanent Magnet Quadrupoles . High-gradient quadrupoles achieving a gradient greater than 100 T/m are key components for handling laser plasma accelerator beams. Permanent magnet technology can be used to build very compact quadrupoles capable of providing a very large gradient up to 500 T/m...

ANTYA High power Computing system with 1 PF speed, designed to support Indian fusion research and is being used for a variety of numerical simulations covering computational fluid dynamics, particle-in-cell, Molecular Dynamics, MHD, AI/DL etc. Architecture of ANTYA HPC Lifting &...

3D Sectional view of SST-1 Vacuum Vessel and Cryostat 3D Sectional view of SST-1 Vacuum Vessel SST-1 Torroidal Field coil TF modules on the support beams Assembly of Prototype Vacuum Vessel and Cryostat Baking Channels On Vessel Surface Radial Port of SST-1 Vacuum Vessel Lip...

Time evolution of the plasma discharge in ADITYA U Tokomak

Cryogenic Vacuum Barrier developed for Superconducting Feeder System of SST-1.

ITER-India completed the manufacturing of the one of the nine procurement packages in active collaboration with M/s Avasarala Technologies, Bengaluru. The package termed as “in-wall shields” is a complex assembly of ~9000 borated steel blocks. CAD Model of In-Wall Shield Assembly...

A neutral beam system for producing hydrogen ion beam current up to 90 A at energy of 55 keV was designed and developed at IPR. The system was designed to deliver 1.7 MW neutral beam power to SST-1 tokamak for the purpose of providing auxiliary heating and current drive to the plasma of the...

Helicon Plasma Source (HeliPS) Laboratory at CPP-IPR is actively engaged in performing experiments in various gases such as Argon, Oxygen, and Hydrogen etc HeliPS System Plasma inside the glass chamber of the HeliPS system Schematic of the HeliPS system