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

Fuente: arXiv
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Autores principales: Hoque, SK Injamul, Raj, Harshita, Dey, Ritu, Banerjee, Soumitra, Komal, Singh, Kaushlender, Dolui, Suman, Kumar, Ankit, Kumawat, Ashok, Hegde, Bharat, Patel, Sharvil, Patel, Kiran, Kumar, Rohit, Aich, Suman, Gautam, Pramila, Nagora, Umesh, Adhiya, Asha N, Jadeja, K. A., Patel, K. M., Patel, Ankit, Tanna, R. L., Ghosh, Joydeep
Formato: Preprint
Publicado: 2025
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author Hoque, SK Injamul
Raj, Harshita
Dey, Ritu
Banerjee, Soumitra
Komal
Singh, Kaushlender
Dolui, Suman
Kumar, Ankit
Kumawat, Ashok
Hegde, Bharat
Patel, Sharvil
Patel, Kiran
Kumar, Rohit
Aich, Suman
Gautam, Pramila
Nagora, Umesh
Adhiya, Asha N
Jadeja, K. A.
Patel, K. M.
Patel, Ankit
Tanna, R. L.
Ghosh, Joydeep
author_facet Hoque, SK Injamul
Raj, Harshita
Dey, Ritu
Banerjee, Soumitra
Komal
Singh, Kaushlender
Dolui, Suman
Kumar, Ankit
Kumawat, Ashok
Hegde, Bharat
Patel, Sharvil
Patel, Kiran
Kumar, Rohit
Aich, Suman
Gautam, Pramila
Nagora, Umesh
Adhiya, Asha N
Jadeja, K. A.
Patel, K. M.
Patel, Ankit
Tanna, R. L.
Ghosh, Joydeep
contents 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 parallel heat flux near the last closed flux surface (LCFS) is observed after each pulse. Comparative analysis indicates that pulsed fuelling is more effective in mitigating heat flux with improved core confinement than continuous gas feeding via real-time density control. Analytical and simulation works are also carried out for validation of experimental results. The analytical model shows that SOL width modification cannot be attributed solely to the decrease of temperature due to gas pulse injection; cross-field plasma diffusion also needs to increase. Simulations with the UEDGE code suggest that an increase in both the cross-field diffusion coefficient and inward pinch velocity is necessary to replicate the experimentally observed broadening of the heat flux SOL width. These findings provide insights into efficient SOL heat flux control strategies for future fusion devices.
format Preprint
id arxiv_https___arxiv_org_abs_2508_00339
institution arXiv
publishDate 2025
record_format arxiv
spellingShingle Favorable modifications of Scrape-Off Layer (SOL) heat flux width through pulsed fuelling in ADITYA-U Tokamak
Hoque, SK Injamul
Raj, Harshita
Dey, Ritu
Banerjee, Soumitra
Komal
Singh, Kaushlender
Dolui, Suman
Kumar, Ankit
Kumawat, Ashok
Hegde, Bharat
Patel, Sharvil
Patel, Kiran
Kumar, Rohit
Aich, Suman
Gautam, Pramila
Nagora, Umesh
Adhiya, Asha N
Jadeja, K. A.
Patel, K. M.
Patel, Ankit
Tanna, R. L.
Ghosh, Joydeep
Plasma Physics
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 parallel heat flux near the last closed flux surface (LCFS) is observed after each pulse. Comparative analysis indicates that pulsed fuelling is more effective in mitigating heat flux with improved core confinement than continuous gas feeding via real-time density control. Analytical and simulation works are also carried out for validation of experimental results. The analytical model shows that SOL width modification cannot be attributed solely to the decrease of temperature due to gas pulse injection; cross-field plasma diffusion also needs to increase. Simulations with the UEDGE code suggest that an increase in both the cross-field diffusion coefficient and inward pinch velocity is necessary to replicate the experimentally observed broadening of the heat flux SOL width. These findings provide insights into efficient SOL heat flux control strategies for future fusion devices.
title Favorable modifications of Scrape-Off Layer (SOL) heat flux width through pulsed fuelling in ADITYA-U Tokamak
topic Plasma Physics
url https://arxiv.org/abs/2508.00339