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Fusion Science and Technology
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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.
R. Pampin, A. Cubi, N. Taylor, M. Fabbri, P. Martinez-Albertos, P. Sauvan, Y. LeTonqueze
Fusion Science and Technology | Volume 80 | Number 8 | November 2024 | Pages 1012-1023
Research Article | doi.org/10.1080/15361055.2023.2278375
Articles are hosted by Taylor and Francis Online.
Photoneutrons may be generated in beryllium by energetic gamma rays via the reaction 9Be(γ,n)8Be. In ITER, the beryllium layer of the first wall may be the source of such photoneutrons. During plasma operation, these are of insignificant intensity compared with D-T neutrons from the plasma, but after shutdown, photoneutrons produced by decay gammas from neutron-activated material may be significant enough to impact sensitive electronic components in diagnostic or remote handling equipment that would not otherwise be exposed to neutrons.
Studies have been performed to characterize the expected photoneutron source and to evaluate the fluxes arising in detailed three-dimensional models of the ITER tokamak. The results show photoneutron fluxes approaching 105 n/cm2·s within the vessel and up to 103 n/cm2·s elsewhere within the bioshield 14 days after shutdown. When first-wall panels are being transported to the Hot Cell Facility after irradiation, a photoneutron flux exceeding 104 n/cm2·s within the transfer cask is predicted 21 days after shutdown. The peak values in the surrounding building are between 102 and 103 n/cm2·s at the same time.