Design and Analysis of an Integrated Additively Manufactured Test Article for Plasma-Facing Components

Journal Article · Fri May 09 00:00:00 UTC 2025 · Fusion Science and Technology

DOI: https://doi.org/10.1080/15361055.2025.2476850 · OSTI ID:3002809

Bhat, Ajit  ^[1]; DeVinney, Michael  ^[1]; Gray, Travis K.  ^[1]; Wiggins, Cody S.  ^[1]

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1. Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)

Current plasma-facing components (PFCs) used in helium-cooled divertor modules are complex structures with tungsten tile, steel sleeve components, and cartridges, all assembled in a helium-cooled multiple jet (HEMJ) structure. The goal of this project is to simplify the complex PFC design using additive manufacturing techniques to create a single integrated tungsten test article. Apart from the flexibility this opens up in exploring a wide array of geometries for the article, having a single integrated article significantly reduces the number of joints and parts in the article, thus reducing chances of leaks. A process called electron beam melting has shown to produce very high-density samples and unique geometries, enabling HEMJ or similar designs. To validate and optimize this novel design, the model underwent a series of computational fluid dynamics and finite element analysis simulations to replicate steady-state heat flux in the divertors. The simulations presented in this study consider a steady-state base heat flux of 5 MW/m², with water serving as the coolant. Future research will explore the use of helium as a coolant, simulate edge-localized-mode conditions, and include experimental validation. Since 3D-printed tungsten is anisotropic, the build direction versus build plane of the article are taken into consideration for the test article strength. Because of the high operating temperatures and low ductility of tungsten, thermal creep and brittle fracture are important failure mechanisms to consider. In conclusion, the cap is evaluated with various flow velocities and nozzle diameters, and an optimal design choice is made for which this cap will survive the divertor conditions with a conservative safety margin.

• Research Organization: Oak Ridge National Laboratory (ORNL), Oak Ridge, TN (United States)
• Sponsoring Organization: USDOE Office of Science (SC), Fusion Energy Sciences (FES)
• Grant/Contract Number: AC05-00OR22725
• OSTI ID: 3002809
• Journal Information: Fusion Science and Technology, Journal Name: Fusion Science and Technology Journal Issue: 7 Vol. 81; ISSN 1943-7641; ISSN 1536-1055
• Publisher: Taylor & FrancisCopyright Statement
• Country of Publication: United States
• Language: English