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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.
Takeo Nishitani, Mikio Enoeda, Masato Akiba, Toshihiko Yamanishi, Kimio Hayashi, Hiroyasu Tanigawa
Fusion Science and Technology | Volume 52 | Number 4 | November 2007 | Pages 971-978
Technical Paper | Tritium, Safety, and Environment | doi.org/10.13182/FST07-A1620
Articles are hosted by Taylor and Francis Online.
Japan Atomic Energy Agency (JAEA) plays a role of the principal institute in Japan for the design and the development of a solid breeder (WCSB) blanket and a helium cooled solid breeder (HCSB) blanket, in the ITER Test Blanket Modules (TBM) programt. The WCSB and HCSB modules consist of reduced activation ferritic/martensitic steel, F82H, as the structural material, Li2TiO3 as the tritium breeder material, beryllium or Be-Ti alloy as the neutron multiplier. One of the R&Ds for the WCSB TBM, the mockup of the first wall with embedded cooling channels was fabricated by applying HIP technique. Pebbles of Be12Ti, which is a candidate material for the advanced neutron multiplier, were produced by a small-scale rotating electrode method. Mechanical and chemical properties and irradiation effects have been studied for Be12T pebbles. Both oxidation and steam interaction were about 1/1000 as small as those of beryllium metal, which indicates a possibility to reduce a risk of a water or air ingress accident. The test schedule of TBMs is discussed according to the ITER operation phases.