Optimization of divertor design for Pakistan spherical tokamak
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Ayesha Alam
,
Shahab Ud-Din Khan
Abstract
Handling the power deposition, reducing erosion effects, and plasma configuration are the key factors in the design of a divertor. The design of Pakistan Spherical Tokamak (PST) is based on double-null divertor configuration with actively cooled graphite targets at outer/inner strike point and peak heat flux range capacity of 0.1–0.3 MW/m2. The configuration of PST divertor module is designed with mock-up (used flat type tiles on baffles and dome) and cassette (support PFC and cooling channels) technology. Helium-cooled stage and water-cooled stage are two options for divertor. Therefore, one part of this research is focused on water-cooling system for the divertor. This paper presents the divertor design for PST with cooling channel and material analysis of the divertor, which is carried out in three phases. In the first phase, the plasma edge temperature, density, particle velocity, input power, heat flux, and surface temperature are estimated. In second phase, physics and engineering design of divertor system has been performed. In the third phase, COMSOL simulation has been performed to analyses the material properties, surface temperature rise (∆T °C) at stable heat flux, and thermal hydraulic system for the divertor. It is found from the analysis that the specific heat flux of 0.3 MW/m2 up to 3 s is the safe zone limit. The R & D work ratifies that manufacturing and installation processes are plausible for the proposed divertor design. This design is able to meet the requirement of PST. However, increasing time or specific heat flux beyond these limits would require redesigning of the cooling channel.
Funding source: IAEA Co-ordinated research project
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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Artikel in diesem Heft
- Frontmatter
- An approach for an extension of the deflagration model in containment code system COCOSYS to separate burned and unburned atmosphere via junctions
- Neutronic analysis of the European sodium cooled fast reactor with Monte Carlo code OpenMC
- Identification and tracing of radionuclides in low- and medium-activity liquid radwaste sources of G.A. Siwabessy reactor
- Performance evaluation of a currently in-use dry storage cask design for spent accident tolerant fuel loading case under normal operation condition
- Optimization of divertor design for Pakistan spherical tokamak
- Role of impurity and thermal noise on the radiation sources in ITER using DT fuel
- An investigation of multistream plate-fin heat exchanger modelling and design: a review
- Ensuring safety of new, advanced small modular reactors for fundamental safety and with an optimal main heat transport systems configuration
- Study on calculation model and risk area of radionuclide diffusion in coastal waters under nuclear leakage accidents with different levels
- Optimization of 200 MWt HTGR with ThUN-based fuel and zirconium carbide TRISO layer
- Experimental study on boiling heat transfer of γ-Fe2O3 nanofluids on a downward heated surface
- Evaluating the influence of radial power heterogeneity of fuel rod on its temperature in an accelerator driven subcritical system
- Heat transfer enhancement of heat exchanger using rectangular channel with cavities
- Calendar of events
