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Second round of Launch Pad selections includes eight newcomers
The National Reactor Innovation Center at Idaho National Laboratory has announced 13 project selections across 12 companies for the Nuclear Energy Launch Pad, a Department of Energy–led program that integrates reactor and fuel facility authorization, testing, and deployment support for private nuclear developers.
The Launch Pad emerged from the Reactor Pilot Program and Fuel Line Pilot Program.
According to INL, projects selected include reactor development and nuclear fuel cycle advancements, including fabrication, enrichment, and conversion technologies.
Chiara Mistrangelo, Leo Bühler
Fusion Science and Technology | Volume 60 | Number 2 | August 2011 | Pages 798-803
Computational Tools, Modeling & Validation | Proceedings of the Nineteenth Topical Meeting on the Technology of Fusion Energy (TOFE) (Part 2) | doi.org/10.13182/FST11-A12483
Articles are hosted by Taylor and Francis Online.
In the framework of the study of a European helium cooled lead lithium blanket concept for ITER, numerical tools are developed to complement experimental activities. Full capability to simulate numerically the global magnetohydrodynamic flow and pressure distributions resulting from the interaction of the liquid metal with the strong plasma confining magnetic field is not achieved yet. Calculations should support the selection and validation of physical models for 3D coupled phenomena, like magneto-convection, as well as for corrosion and tritium permeation processes. Moreover, simulations help to interpret measurement data and to enhance the development of extrapolation procedures from small-scale experiments to a DEMO reactor.The present paper summarizes the mathematical algorithm and modeling requirements for accurate predictions of liquid-metal flows under very intense magnetic fields in geometries with arbitrary electric conductivity of the walls. The Lorentz force term and additional equations determining electric current density and potential have been introduced in a consistent and conservative way into the existing hydrodynamic open source code OpenFOAM. The use of non-orthogonal corrections leads to a significant improvement of the MHD code at fusion relevant strong magnetic fields. The discussion focuses on benchmark problems used to validate the new developed tool and on the treatment in OpenFOAM of MHD flows in geometries with walls of finite electric conductivity. According to the authors' knowledge, the implementation of this capability in this open source code has not been reported so far in other references.