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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.
L. El-Guebaly, P. Wilson, D. Henderson, L. Waganer, R. Raffray, ARIES Team
Fusion Science and Technology | Volume 44 | Number 2 | September 2003 | Pages 405-409
Technical Paper | Fusion Energy - Tritium and Safety and Environment | doi.org/10.13182/FST03-A368
Articles are hosted by Taylor and Francis Online.
Heavy ion beam driven inertial fusion energy (IFE) power plants employ liquid wall materials to protect the structure against the energetic x-rays, ions, and debris emitted from the target following each shot. The objective of this assessment is to identify the radiological issues of the candidate liquid wall materials (Pb, LiPb, Sn, and Flibe) using the ARIES-IFE radiation chamber environment. The issues to be addressed include the radioactivity level and liquid waste minimization for waste management. Specifically, the liquids are evaluated with regard to the Class C limitation for waste disposal, a top-level requirement for all ARIES power plant designs. Two extreme cases were analyzed; the worst case is separation of the liquid wall material (highest radiation exposure) and the breeder (lowest radiation exposure), and the best case is the mixing of the two liquid streams. Both tangential and porous wall injection schemes were examined. Pb and LiPb are more radioactive than Sn and Flibe. For the liquid breeder system, the porous wall injection scheme with mixed liquid flows results in the lowest waste disposal rating and smallest waste stream achieved in our study.