activity
20222026
most citedImproved Heat and Particle Flux Mitigation in High Core Confinement, Baffled, Alternate Divertor Configurations in the TCV tokamak

16 citations · 31 across the 11 of their papers we have counts for

collaborators

11 papers

physics.plasm-ph2026

Production of high-quality plasma discharges via real-time control of plasma current ramp-up using neutral gas injection in Aditya-U tokamak

Suman Dolui, Praveenlal Edappala, Kaushlender Singh +13

Robust control of plasma current ramp-up is an absolute necessity, as an efficient and uncontaminated plasma current ramp-up is essential for achieving prolonged, high-pressure tok…

physics.plasm-ph2026

Development of a thin-target hard X-ray bremsstrahlung detection system to study confined runaway electrons in Aditya-U Tokamak

Suman Dolui, Santosh Pandya, J. Kumar +23

A specially shielded CdTe detector based hard X-ray (HXR) monitoring system equipped with a lead collimator has been developed and installed on the Aditya-U tokamak to investigate…

physics.plasm-ph2026

Effect of LH and ECR waves on plasma parameters in ADITYA Upgrade tokamak

S. Aich, S. Dolui, K. Singh +29

The plasma discharges in ADITYA Upgrade Tokamak are produced by means of transformer action, in which Ohmically created plasma is driven by means of a secondary loop voltage. Due t…

physics.plasm-ph2025

PRISM: A MATLAB-Based Application for Structured Probe Data Management and Visualization in Tokamak Diagnostics

Priyanka Verma, Subhojit Bose, Harshita Raj +1

The successful operation of tokamak experiments requires accurate documentation, tracking, and visualization of diagnostic instruments, particularly electrical probes. Traditionall…

physics.plasm-ph2025

Favorable modifications of Scrape-Off Layer (SOL) heat flux width through pulsed fuelling in ADITYA-U Tokamak

SK Injamul Hoque, Harshita Raj, Ritu Dey +19

Enhancement of the scrape-off layer (SOL) heat flux width has been observed in the ADITYA-U Tokamak following the injection of short fuel gas pulses. A notable reduction in paralle…

physics.plasm-ph2025

Effect of convective transport in edge/SOL plasmas of ADITYA-U tokamak

Ritu Dey, Joydeep Ghosh, Tanmay M. Macwan +6

The 2-D edge plasma fluid transport code, UEDGE has been used to simulate the edge region of circular limiter plasmas of ADITYA-U for modelling the measured electron density profil…

physics.plasm-ph2025

A multi-purpose reciprocating probe drive system for studying the effect of gas-puffs on edge plasma dynamics in the ADITYA-U tokamak

Kaushlender Singh, Bharat Hegde, Ashok K. Kumawat +24

This article reports the development of a versatile high-speed reciprocating drive system (HRDS) with interchangeable probe heads to characterize the edge plasma region of ADITYA-U…

physics.plasm-ph2025★ 1 cited

Stabilization of sawteeth instability by short gas pulse injection in ADITYA-U tokamak

Suman Dolui, Kaushlender Singh, Bharat Hegde +28

Experiments on ADITYA-U tokamak show a marked enhancement in the sawtooth period by application of short gas puffs of fuel that cause a modification of the radial density profile.…

physics.plasm-ph2024

MHD activity induced coherent mode excitation in the edge plasma region of ADITYA-U Tokamak

Kaushlender Singh, Suman Dolui, Bharat Hegde +28

In this paper, we report the excitation of coherent density and potential fluctuations induced by magnetohydrodynamic (MHD) activity in the edge plasma region of ADITYA-U Tokamak.…

physics.plasm-ph2022★ 14 cited

Power exhaust and core-divertor compatibility of the baffled snowflake divertor in TCV

Sophie Gorno, Claudia Colandrea, Olivier Février +8

A baffled Snowflake Minus Low-Field Side (SF-LFS) is geometrically-optimised in TCV, increasing divertor neutral pressure, to evaluate the roles of divertor closure (comparing with…

physics.plasm-ph2022★ 16 cited

Improved Heat and Particle Flux Mitigation in High Core Confinement, Baffled, Alternate Divertor Configurations in the TCV tokamak

Harshita Raj, C. Theiler, A. Thornton +13

Nitrogen seeded detachment has been achieved in the Tokamak a Configuration Variable (TCV) in advanced divertor configurations (ADCs), namely X-divertor and X-point target, with an…