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Spent fuel recycling and conditioning topic of U.S.-Japan meeting
Officials with the Department of Energy’s Office of Environmental Management discussed spent nuclear fuel recycling and conditioning with counterparts from Japan during the 13th U.S.-Japan Technical Meeting of the Civil Nuclear Energy Research and Development Working Group, held recently in Santa Fe, N.M.
R. Pampin, M. J. Loughlin, M. J. Walsh
Fusion Science and Technology | Volume 56 | Number 2 | August 2009 | Pages 751-755
Nuclear Analysis | Eighteenth Topical Meeting on the Technology of Fusion Energy (Part 2) | doi.org/10.13182/FST56-751
Articles are hosted by Taylor and Francis Online.
Systematic analysis of the radiation fields throughout the ITER core LIDAR diagnostic system were performed to support the design optimisation and assessment process, aiming at achieving the required performance in terms of reliability, occupational safety and interface with neighboring systems. Neutron, photon, nuclear heat and material activation responses were estimated for a variety of configurations, and improved using a combination of analytical "rules of thumb" and numerical computations with the ATTILATM and FISPACT codes. The neutron flux at the backplate of the port plug was significantly reduced (to ∼2x107 n/cm2-s) by fine-tuning the reference geometry of the laser labyrinth, and guidelines were provided for quick estimation of the effect of future design changes. The current design has adequate lifetime of essential optical components, in particular absorption in collection windows below ∼1%, and reduced dose to workers during maintenance according to the ALARA principle.