Transient thermal analysis for optimal armor material in upgraded mockup for PST using MOOSE Framework

Abstract The divertor mockup design for the Pakistan Spherical Tokamak (PST) needs several improvements. These include reducing the total number of upper and lower divertors to 32 and enhancing the heat load capacity to 1 MW/m 2 . This study involves a thermal analysis of the upgraded divertor design for PST through simulation using MOOSE Framework. The simulation involves two steps – validation and thermal analysis. Validation is achieved by modeling 1D and 2D conduction problems in MOOSE Framework and comparing the results with the analytical solutions. The thermal analysis of a mockup of the upgraded PST divertor configurations with tungsten and graphite as armor materials under peak thermal heat load conditions of 1 MW/m 2 is performed. The results of the transient thermal analysis reveal that the mockup surface temperature rise for tungsten remains lower than that for graphite. The findings of the study indicate that both tungsten and graphite mockups can sustain a specific heat flux of 1 MW/m 2 for up to 3 s. However, even being a good conductor of heat, tungsten’s high atomic number (Z) poses challenges in plasma stability. On the other hand, graphite when paired with an efficient cooling system for controlling surface temperature rise is a superior armor material due to its affordability, ease of availability, and better compatibility with plasma environments. It is recommended as the preferred armor material for the upgraded divertor mockup in the PST system.

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Publication Details

Journal
Kerntechnik
Published
2024-11-19
DOI
https://doi.org/10.1515/kern-2024-0077
Citations
6
Primary Topic
Fusion materials and technologies
Type
article
Field-Weighted Citation Impact
0.70
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article

Transient thermal analysis for optimal armor material in upgraded mockup for PST using MOOSE Framework

Manzoor Ahmed, Muhammad Ilyas, Shahab Ud‐Din Khan, Muhammad Abdullah et al.
6 citations
Kerntechnik
Fusion materials and technologies
0.70
article

Transient thermal analysis for optimal armor material in upgraded mockup for PST using MOOSE Framework

Manzoor Ahmed, Muhammad Ilyas, Shahab Ud‐Din Khan, Muhammad Abdullah, Habib Ur Rahman, Ali A-K. Hussain
article en
6 citations

Abstract

Abstract The divertor mockup design for the Pakistan Spherical Tokamak (PST) needs several improvements. These include reducing the total number of upper and lower divertors to 32 and enhancing the heat load capacity to 1 MW/m 2 . This study involves a thermal analysis of the upgraded divertor design for PST through simulation using MOOSE Framework. The simulation involves two steps – validation and thermal analysis. Validation is achieved by modeling 1D and 2D conduction problems in MOOSE Framework and comparing the results with the analytical solutions. The thermal analysis of a mockup of the upgraded PST divertor configurations with tungsten and graphite as armor materials under peak thermal heat load conditions of 1 MW/m 2 is performed. The results of the transient thermal analysis reveal that the mockup surface temperature rise for tungsten remains lower than that for graphite. The findings of the study indicate that both tungsten and graphite mockups can sustain a specific heat flux of 1 MW/m 2 for up to 3 s. However, even being a good conductor of heat, tungsten’s high atomic number (Z) poses challenges in plasma stability. On the other hand, graphite when paired with an efficient cooling system for controlling surface temperature rise is a superior armor material due to its affordability, ease of availability, and better compatibility with plasma environments. It is recommended as the preferred armor material for the upgraded divertor mockup in the PST system.

KerntechnikVol. 89(6)
Pakistan Institute of Engineering and Applied Sciences (PK)
Openalex Percentile: Top 29%
Fusion materials and technologies
0.70
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Transient thermal analysis for optimal armor material in upgraded mockup for PST using MOOSE Framework — Manzoor Ahmed, Muhammad Ilyas, et al. · Kerntechnik (2024) | TGRS Research Map | TGRS