Subrata Pradhan
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View article: Adaptive Control Strategies for Enhancing the Integration and Stability of Renewable Energy Sources in Smart Microgrids
Adaptive Control Strategies for Enhancing the Integration and Stability of Renewable Energy Sources in Smart Microgrids Open
The growing use of renewable energy sources (RES) in small-scale power systems brings about major obstacles in keeping the power grid steady and dependable because RES naturally fluctuates and is not always available. This study suggests a…
View article: Unravelling the non-Markovian spin-boson model and quantum quasi-Otto cycle
Unravelling the non-Markovian spin-boson model and quantum quasi-Otto cycle Open
We use the spin-boson model to describe the dynamics of a two-level atom interacting with Fabry-Pérot cavity modes. We solve the Schrödinger equation for the system-bath model without the Born-Markov approximation to derive the non-Markovi…
View article: Development of Precise Low Value Capacitance Measurement System for Cryogenics Two Phase Flow Application
Development of Precise Low Value Capacitance Measurement System for Cryogenics Two Phase Flow Application Open
In cryogenic two phase flow, it is always challenging to measure the quality and void fraction. In this regard, an effort has been made to indigenously develop an electronic circuit to measure the void fraction by measuring the capacitance…
View article: Prediction of Helium Vapor Quality in Steady-State Two-Phase Operation of SST-1 Superconducting Toroidal Field Magnets
Prediction of Helium Vapor Quality in Steady-State Two-Phase Operation of SST-1 Superconducting Toroidal Field Magnets Open
Steady State Superconducting Tokamak (SST-1) at the Institute for Plasma\nResearch (IPR) is an operational device and is the first superconducting\nTokamak in India. Superconducting Magnets System (SCMS) in SST-1 comprises of\nsixteen Toro…
View article: Two phase helium cooling characteristics in Cable-in-Conduit Conductors
Two phase helium cooling characteristics in Cable-in-Conduit Conductors Open
Cable-in-Conduit Conductors (CICCs) are used in the fabrication of superconducting fusion grade magnets.It acts as a narrow cryostat to provide cryo-stability with direct contact of coolant fluid to conductor.The superconducting magnets ar…
View article: Two phase helium cooling characteristics in Cable-in Conduit Conductors
Two phase helium cooling characteristics in Cable-in Conduit Conductors Open
Cable-in-Conduit Conductors (CICCs) are used in the fabrication of superconducting fusion grade magnets. It acts as a narrow cryostat to provide cryo-stability with direct contact of coolant fluid to conductor. The superconducting magnets …
View article: Conceptual design of Dump resistor for Superconducting CS of SST-1
Conceptual design of Dump resistor for Superconducting CS of SST-1 Open
Under upgradation activities for SST-1, the existing resistive central solenoid (CS) coil will be replaced with Nb3Sn based superconducting coil. Design of Central solenoid had been completed and some of the initiative has already taken fo…
View article: Gas Fuelling System for SST-1Tokamak
Gas Fuelling System for SST-1Tokamak Open
SST-1 Tokamak, the first Indian Steady-state Superconducting experimental device is at present under operation in the Institute for Plasma Research. For plasma break down & initiation, piezoelectric valve based gas feed system is implement…
View article: Engineering design and integration of in-vessel single turn segmental coil in vacuum vessel of SST-1
Engineering design and integration of in-vessel single turn segmental coil in vacuum vessel of SST-1 Open
SST-1 tokamak is having the error field due to unsymmetrical positioning of Toroidal field coils which push the plasma to inner side from its major radius of 1100 mm. hence it is required to install the In-vessel Coil (PF6) at a location o…
View article: Quality control of FWC during assembly and commissioning in SST-1 Tokamak
Quality control of FWC during assembly and commissioning in SST-1 Tokamak Open
First Wall Components (FWC) of SST-1 tokamak, which are in the immediate vicinity of plasma, comprises of limiters, divertors, baffles, passive stabilizers designed to operate long duration (∼1000 s) discharges of elongated plasma. All FWC…
View article: Conceptual & Engineering Design of Plug-in Cryostat Cylinder for Super-Conducting Central Solenoid of SST-1
Conceptual & Engineering Design of Plug-in Cryostat Cylinder for Super-Conducting Central Solenoid of SST-1 Open
SST-1, country's first indigenously built steady state super-conducting tokamak is planned to be equipped with an Nb3Sn based superconducting central solenoid, which will replace the existing copper conductor TR1 coil for the purpose of Oh…
View article: Indigenously developed bending strain setup for I-V characterization of superconducting tapes and wires
Indigenously developed bending strain setup for I-V characterization of superconducting tapes and wires Open
An indigenously developed bending strain setup to examine the effect of pure bending on critical current of superconducting tapes and strands has been presented in this paper. This set up is capable of applying various bending radius in si…
View article: Upgradation plans of SST-1 Cryogenics system at IPR
Upgradation plans of SST-1 Cryogenics system at IPR Open
Steady State Superconducting Tokamak (SST-1) is India's First Superconducting Tokamak and has Toroidal Field (TF) and Poloidal Field (PF) superconducting coils along with the cold mass support structure weighing about 38 ton of cold mass. …
View article: Prototyping of radial plates for fusion relevant superconducting magnets
Prototyping of radial plates for fusion relevant superconducting magnets Open
The fabrication trials for prototype radial plate to support its conceptual design and development for fusion relevant superconducting magnet have been discussed in this paper. The simulation approach with CAD has been presented for protot…
View article: Commissioning and experimental validation of SST-1 plasma facing components
Commissioning and experimental validation of SST-1 plasma facing components Open
Plasma facing components of SST-1 are designed to withstand an input heat load of 1.0 MW/m2. They protect vacuum vessel, auxiliary heating source i.e. RF antennas, NBI and other in-vessel diagnostic from the plasma particles and high radia…
View article: Observation of MHD phenomenon for SST-1 superconducting tokamak
Observation of MHD phenomenon for SST-1 superconducting tokamak Open
Steady State Superconducting Tokamak (SST-1) is a medium size Tokamak (major radius = 1.1 m, minor radius = 0.2 m) and is operational at the Institute for Plasma Research (IPR), India. In the last few experimental campaigns SST-1 has succe…
View article: Development, Integration and Testing of Automated Triggering Circuit for Hybrid DC Circuit Breaker
Development, Integration and Testing of Automated Triggering Circuit for Hybrid DC Circuit Breaker Open
A novel concept of Hybrid DC circuit breaker having combination of mechanical switch and static switch provides arc-less current commutation into the dump resistor during quench in superconducting magnet operation. The triggering of mechan…
View article: Assembly & Metrology of First Wall Components of SST-1
Assembly & Metrology of First Wall Components of SST-1 Open
First Wall Components (FWC) of SST-1 tokamak, which are in the immediate vicinity of plasma comprises of limiters, divertors, baffles, passive stabilizers are designed to operate long duration (1000 s) discharges of elongated plasma. All F…
View article: Initial results in SST-1 after up-gradation
Initial results in SST-1 after up-gradation Open
SST-1 Tokamak has recently completed the 1st phase of up-gradation with successful installation and integration of all its First Wall components. The First Wall of SST-1 comprises of ∼ 3800 high heat flux compatible graphite tiles being as…
View article: Study of Transport and Micro-structural properties of Magnesium Di-Boride Strand under react and bend mode and bend and react mode
Study of Transport and Micro-structural properties of Magnesium Di-Boride Strand under react and bend mode and bend and react mode Open
I-V characterization of commercial multi-filamentary Magnesium Di-Boride (MgB2) wire of diameter 0.83 mm were studied in Cryocooler at self-field I-V characterization system under both react and bend mode and bend and react mode for a rang…
View article: The Determination of Plasma Radial Shafranov Shift (ΔR) and Vertical Shift (ΔZ) experimentally using Magnetic probe and Flux loop Method for SST-1 Tokamak
The Determination of Plasma Radial Shafranov Shift (ΔR) and Vertical Shift (ΔZ) experimentally using Magnetic probe and Flux loop Method for SST-1 Tokamak Open
The radial Shafranov shift (ΔR) and vertical shift (ΔZ) has been calculated for steady state superconducting tokamak (SST-1) experimentally using magnetic probes and flux loops. The SST-1 plasma at the present phases of operations is circu…
View article: Overall behaviour of PFC integrated SST-1 vacuum system
Overall behaviour of PFC integrated SST-1 vacuum system Open
As a part of phase-I up-gradation of Steady-state Superconducting Tokamak (SST-1), Graphite Plasma Facing Components (PFCs) have been integrated inside SST-1 vacuum vessel as a first wall (FW) during Nov 14 and May 2015. The SST-1 FW has a…
View article: RF assisted Glow Discharge Condition experiment for SST-1 Tokamak
RF assisted Glow Discharge Condition experiment for SST-1 Tokamak Open
Impurity control reduces the radiation loss from plasma and hence enhances the plasma operation. Oxygen and water vapors are the most common impurities in tokamak devices. Water vapour can be reduced with extensive baking while in order to…
View article: Design and Integration of SMBI System for SST-1 Tokamak
Design and Integration of SMBI System for SST-1 Tokamak Open
Supersonic molecular beam injection (SMBI) is one of the most effective fuelling methods for injecting neutral particles at very high velocity into the plasma core. Due to higher speed and lower divergence, the beam penetrates several cent…
View article: Design of new central solenoid for SST-1
Design of new central solenoid for SST-1 Open
The key role of central solenoid (CS) magnet of a Tokamak is for gas breakdown, ramp up and maintaining of plasma current. The magnetic flux change in CS along with other PF coils generates magnetic null and induces electric field in toroi…
View article: Baking and helium glow discharge cleaning of SST-1 Tokamak with graphite plasma facing components
Baking and helium glow discharge cleaning of SST-1 Tokamak with graphite plasma facing components Open
Graphite plasma facing components (PFCs) were installed inside the SST-1 vacuum vessel. Prior to installation, all the graphite tiles were baked at 1000 °C in a vacuum furnace operated below 1.0 × 10-5 mbar. However due to the porous struc…
View article: Experience of 12 kA / 16 V SMPS during the HTS Current Leads Test
Experience of 12 kA / 16 V SMPS during the HTS Current Leads Test Open
As a part of up gradation plans in SST-1 Tokamak, one pair of 3.3 kA rated prototype hybrid current leads were developed using Di-BSCCO as High Temperature Superconductors (HTS) and the copper heat exchanger. In order to validate the manuf…