India's progress in fusion energy.

Karthi

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42GHz Gyrotron.jpg



Latest 42 GHz Gyrotron for India's fusion reactor may be For SST 2 (Not Sure).


Gyrotrons are the most advanced high power sources of millimeter wavelength radiation.


They have been used for many years in electron-cyclotron-wave (ECW) systems of many existing fusion installations.

Typically modern gyrotrons produce power of 0.5...0.8 MW in pulses of 2-3 seconds, or lower power in longer pulses (e.g. 300-400 kW in pulses up to 10-15 seconds). For the next generation of fusion installations, such as ITER systems based on gyrotrons capable to produce 1MW/CW radiation are considered.
 

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LaBr3(Ce) Detector Based HXR Spectroscopy in Aditya-U Tokamak

Study of hard X-ray (HX) spectrum is an important tool to understand the runaway electrons (RE) behavior present in the tokamak plasma as these energetic electrons, especially those generated during disruption, represent a major threat to toka-mak plasma devices in terms of melting and damaging the plasma-facing component (PFC) and thereby reduced the lifetime of first wall.

A LaBr3(Ce) detector based spectroscopic diagnostic has been set up on the Aditya tokamak to measure the HX spectrum. This diagnostic consists of a photomultiplier tube and multi-channel analyzer (MCA) along with the detector, viewing the whole plasma tangentially along a line of sight terminating on the limiter. The system has total ~2000 channels covering the energy range of 75 keV to few MeV and spectral resolution of ~19.86vkeV at 662 keV, which is lowest among the many scin-tillation based detectors. The typical HX spectra which integrated over the discharge duration. The spectrum has been ob-served in the energy range of around ~ 75 keV to 3 MeV and is continuum in nature.

The spectra is calibrated in energy as well as photon space. The measured spectrum shows peaks within ~ 85 to 150 keV for the analyzed discharges. The peak position of HX spectra peak height is directly related to the maximum population of HX flux, and subsequently can be approximately attributed to RE population, at a particular energy. The HX spectra peak height exhibits an inversely proportional nature with the plasma thermal temperature. Hence, the lower value of energy at peak height at higher thermal Te indicates that the plasma is mostly dominated by lower energy RE.
FB_IMG_1591283835254.jpg
 

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ITER Cryostat Lower Cylinder completed, wrapped and moved from Cryostat workshop to intermedia...jpg





India handed over crucial Parts for ITER

The Upper Cylinder, one of the four major sections of the Cryostat, weighing nearly 430 tons, has been completely manufactured along with sub-assembly, and handed over to ITER Organization, France. With the completion 3 of 4 sections of the Cryostat viz. Base Section, Lower Cylinder, Upper Cylinder, now the Cryostat manufacturing is 80% complete. The Base Section previously handed over by India to IO, has now been moved into the ITER Assembly Hall, initiating preparations for its installation in the Tokamak pit soon. The Cryostat when fully manufactured and assembled will be the largest vessel of its kind in the world. It is the outer vacuum boundary of the ITER Tokamak.
 

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Integration of L& T Cryostat on ITER

Lifting Operation of Cryostat Base Section, ~1250 tons.jpg



Lifting Operation of Cryostat Base Section, ~1250 tons.

Cryostat Base Section being lowered in the Tokamak pit.jpg


Cryostat Base Section being lowered in the Tokamak pit.

Cryostat Base Section positioned in the Tokamak Pit1.jpg


Cryostat Base Section positioned in the Tokamak Pit1

Cryostat Base Section positioned in the Tokamak Pit2.jpg

Cryostat Base Section positioned in the Tokamak Pit2
 

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Helicon Plasma Source (HeliPS) Laboratory at CPP-IPR is actively engaged in performing experiments in various gases such as Argon, Oxygen, and Hydrogen etc

image of the HeliPS system.jpg


HeliPS System

Plasma inside the glass chamber of the HeliPS system .jpg


Plasma inside the glass chamber of the HeliPS system


Schematic of the HeliPS system.jpg


Schematic of the HeliPS system
 

Karthi

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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 SST-1 tokamak.


The hydrogen positive ion source on the SST-1 NBI test stand.jpg




The hydrogen positive ion source on the SST-1 NBI test stand
 

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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.


3D CAD model of the In-Wall Shield assembly of ITER at IPR.jpg


CAD Model of In-Wall Shield Assembly

manufactured borated steel plate assemblies , assembled in vessel sectors for ITER manufacture...jpg



manufactured borated steel plate assemblies , assembled in vessel sectors for ITER manufactured in Korea
 

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3D Sectional view of SST-1 Vacuum Vessel and Cryostat.jpg


3D Sectional view of SST-1 Vacuum Vessel and Cryostat

3D Sectional view of SST-1 Vacuum Vessel.jpg


3D Sectional view of SST-1 Vacuum Vessel

SST-1 Torroidal Field coil.jpg


TF Module with tackle.png


SST-1 Torroidal Field coil

TF modules on the support beams.jpg

TF modules on the support beams

Assembly of Prototype Vacuum Vessel and Cryostat.jpg


Assembly of Prototype Vacuum Vessel and Cryostat

Baking Channels On Vessel Surface.jpg

Baking Channels On Vessel Surface

Radial Port of SST-1 Vacuum Vessel.jpg


Radial Port of SST-1 Vacuum Vessel

Lip Angle machining of Vessel Sector.jpg


Lip Angle machining of Vessel Sector

Helium Leak Testing of Baking Channels.jpg


Helium Leak Testing of Baking Channels
 

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The “ANTYA” HPC system .jpg

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 the “ANTYA” HPC system .jpg


Architecture of ANTYA HPC

Lifting and Installation Operation of Cryostat Lower Cylinder in Tokamak Pit  3.jpg
Lifting and Installation Operation of Cryostat Lower Cylinder in Tokamak Pit  2.jpg

Lifting and Installation Operation of Cryostat Lower Cylinder in Tokamak Pit  .jpg


Lifting & installation of Indian made cryostat at ITER
 

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Permanent Magnet Quadrupoles .jpg
Permanent Magnet Quadrupole .jpg



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.

Drift Tubes Linac cavity with assembled Drift Tubes.jpg



Drift Tube Linac cavity with Assembled Drift Tubes

Drift Tubes located aperiodically inside DTL .jpg


Drift Tube .jpg


Drift Tube

20 MeV Alvarez DTL – RF input view .jpg


20 MeV Alvarez DTL developed at BARC.jpg



20 MeV Alvarez DTL developed at BARC

The DTL uses to accelerate particles . The permanent magnet quadrupoles (PMQ) are used to focus the beam in the DTL.

Developed Magnet .jpg


electromagnets developed for using in the accelerator
 

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