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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.
Enrico Lucon, Rik-Wouter Bosch, Lorenzo Malerba, Steven Van Dyck, Marc Decréton
Fusion Science and Technology | Volume 47 | Number 4 | May 2005 | Pages 895-900
Technical Paper | Fusion Energy - Fusion Materials | doi.org/10.13182/FST05-A801
Articles are hosted by Taylor and Francis Online.
For the last 20 years, fusion material programs in Europe, Japan and US have been focused on developing Reduced Activation Ferritic/Martensitic (RAFM) steels as prominent structural materials. In the European Union, within the Long Term Programme of EFDA (European Fusion Development Agreement), considerable effort has been spent by several scientific institutions for the characterization and optimization of the European reference RAFM steel (EUROFER97). Within the Belgian Nuclear Centre (SCKCEN), an integrated approach to the characterization of EUROFER97 is being consistently applied; this includes: neutron irradiations in the BR2 reactor and subsequent characterization of the unirradiated and irradiated mechanical properties (tensile, impact and fracture toughness tests); investigation of environmentally assisted cracking (more specifically, study of the influence of irradiation damage on both EAC and embrittlement in Pb-Li alloys); multiscale modelling of radiation effects and specific effects on Fe-Cr systems, using methods which range from the atomic level (MD - Molecular Dynamics) to the mesoscopic level (KMC - Kinetic Monte Carlo). This paper will provide a general overview of the above mentioned investigations, as well as highlights of the most significant results obtained in the different fields of activity.
