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WIPP: Lessons in transportation safety
As part of a future consent-based approach by the federal government to site new deep geologic repositories for nuclear waste, local communities and states that are considering hosting such facilities are sure to have many questions. Currently, the Waste Isolation Pilot Plant in New Mexico is the only example of such a repository in operation, and it offers the opportunity for state and local officials to visit and judge for themselves the risks and benefits of hosting a similar facility. But its history can also provide lessons for these officials, particularly the political process leading up to the opening of WIPP, the safety of WIPP operations and transportation of waste from generator facilities to the site, and the economic impacts the project has had on the local area of Carlsbad, as well as the rest of the state of New Mexico.
S. I. Abdel-Khalik, M. Yoda
Fusion Science and Technology | Volume 47 | Number 3 | April 2005 | Pages 601-609
Technical Paper | Fusion Energy - Inertial Fusion Technology | doi.org/10.13182/FST05-A752
Articles are hosted by Taylor and Francis Online.
This paper provides an overview of experimental and numerical studies conducted at Georgia Tech to assess the fluid dynamics aspects of liquid protection schemes for fusion energy reactors. The problems described here include: (1) Dynamics of slab jets for thick liquid protection, including the effect of nozzle design, flow conditioning, and boundary layer cutting on jet surface smoothness; (2) Primary turbulent breakup of turbulent liquid sheets and forced thin liquid films, and quantification of the associated hydrodynamic source term; (3) Dynamics of forced films on downward-facing flat and curved surfaces, including film detachment and flow around beam ports; (4) Free-surface topology and drop detachment from downward-facing porous wetted walls; and (5) Thermocapillary effects and associated design constraints for liquid-film-protected divertors and first walls.The experimental data and validated numerical models developed in these studies allow reactor designers to identify design windows for successful operation of liquid-protected first walls and plasma facing components in inertial and magnetic confinement systems.