Determination of limiter design and material composition of MT-II spherical tokamak
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Shahab Ud-Din Khan
,
Muhammad Abdullah
Abstract
MT-II is a spherical tokamak with a major radius of 0.15 m and a minor radius of 0.09 m, currently under development at the Pakistan Tokamak Plasma Research Institute. It is designed with a higher elongation of 2.67. This paper presents the design and material analysis of the limiter configuration for the MT-II tokamak, which is being carried out in two phases. In the first phase, theoretical studies and calculations are performed to estimate the plasma edge temperature, density, particle velocity, input power, heat flux, heat load and surface temperature on the limiter tile. In the second phase, computational techniques are applied to analyses the material properties, the maximum/minimum surface temperature rise (∆T °C) at stable heat load and power deposition based on theoretical calculations that will help optimize the design parameters of the limiter. The type of material and the surface temperature of the limiter as well as the general design parameters of MT-II are included in the proposed poloidal limiter. The results suggest that crystalline vein graphite is a suitable candidate for the proposed poloidal limiter. A combination of mechanical and electrical feedthrough techniques are used to improve the performance of the limiter. The proposed limiter is able to meet the requirements of MT-II.
Funding source: Grant-in-Aid from IAEA Co-Ordinated Research Project (CRP-F13018) https://www.iaea.org/projects/crp/f13018
Award Identifier / Grant number: PAK-22840
Acknowledgment
The research team show their gratitude and sincere appreciation to Pakistan Tokamak Plasma Research Institute (PTPRI) initiative for funding and support of this research.
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Author contributions: All the authors have accepted responsibility for the entire content of this submitted manuscript and approved submission.
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Research funding: This project was partially supported by a Grant-in-Aid from IAEA Co-Ordinated Research Project (CRP-F13018) under research grant PAK-22840.
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Conflict of interest statement: The authors declare no conflicts of interest regarding this article.
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Articles in the same Issue
- Frontmatter
- Application of the COCOSYS code in the safety evaluation of Czech nuclear power plants
- Improving of electric network feeding nuclear facility based on multiple types DGs placement
- Design and evaluation of ecological interface for Feedwater Deaerating Tank and Gas Stripper System based on cognitive work analysis
- Evaluation of different integrated burnable absorber materials in fuel assemblies of Bushehr WWER-1000 nuclear reactor
- Effective physical protection system design and implementation at a radiological facility: an integrated and risk management approach
- Determination of limiter design and material composition of MT-II spherical tokamak
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- Calendar of events
Articles in the same Issue
- Frontmatter
- Application of the COCOSYS code in the safety evaluation of Czech nuclear power plants
- Improving of electric network feeding nuclear facility based on multiple types DGs placement
- Design and evaluation of ecological interface for Feedwater Deaerating Tank and Gas Stripper System based on cognitive work analysis
- Evaluation of different integrated burnable absorber materials in fuel assemblies of Bushehr WWER-1000 nuclear reactor
- Effective physical protection system design and implementation at a radiological facility: an integrated and risk management approach
- Determination of limiter design and material composition of MT-II spherical tokamak
- Dynamics effects of tritium reduction on the energy gain of D-T fuel pellet using double cone ignition
- Design of an unattended ore grading measurement system in a uranium mine
- Prediction of heat transfer characteristics in a microchannel with vortex generators by machine learning
- Prediction of nanofluid flows’ optimum velocity in finned tube-in-tube heat exchangers using artificial neural network
- Investigating the in-core 60Co production assembly for open pool type reactor
- Calendar of events
