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Fuel Cycle & Waste Management
Devoted to all aspects of the nuclear fuel cycle including waste management, worldwide. Division specific areas of interest and involvement include uranium conversion and enrichment; fuel fabrication, management (in-core and ex-core) and recycle; transportation; safeguards; high-level, low-level and mixed waste management and disposal; public policy and program management; decontamination and decommissioning environmental restoration; and excess weapons materials disposition.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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The Standards Committee is responsible for the development and maintenance of voluntary consensus standards that address the design, analysis, and operation of components, systems, and facilities related to the application of nuclear science and technology. Find out What’s New, check out the Standards Store, or Get Involved today!
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Latest News
Securing the advanced reactor fleet
Physical protection accounts for a significant portion of a nuclear power plant’s operational costs. As the U.S. moves toward smaller and safer advanced reactors, similar protection strategies could prove cost prohibitive. For tomorrow’s small modular reactors and microreactors, security costs must remain appropriate to the size of the reactor for economical operation.
Doo-Hyun Lim
Nuclear Technology | Volume 156 | Number 2 | November 2006 | Pages 222-245
Technical Paper | Radioactive Waste Management and Disposal | doi.org/10.13182/NT06-A3787
Articles are hosted by Taylor and Francis Online.
Migration of nuclides in a water-saturated high-level radioactive waste repository is analyzed by a newly developed two-dimensional numerical model incorporating a multiple-canister configuration and a nonuniform horizontal flow field of the host rock. The nonuniform flow field is established numerically by obtaining space-dependent groundwater flow velocity vectors using the finite element method. Transport of nuclides is simulated for the instantaneous-pulse-input source condition using the random-walk method. The current study for advection-dominant host rock shows quantitatively that the migration of nuclides in a repository adopting the disposal-pit vertical-emplacement concept is influenced not only by the canister configuration but also by flow boundary conditions, where groundwater flow is considered to be horizontal to the repository plane. The effects of applied hydraulic gradient direction h on nuclide migration become more significant as the number of canisters increases, while the effects are negligible for the single-canister configuration. As the number of canisters increases, the results of nuclide migration with respect to h range more widely and are bounded by two extreme cases. The h orthogonal to the orientation of the disposal tunnel is observed as most advantageous in terms of the isolation of the radionuclide. The single-canister configuration yields conservative results compared with the multiple-canister configuration.