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Materials Science & Technology
The objectives of MSTD are: promote the advancement of materials science in Nuclear Science Technology; support the multidisciplines which constitute it; encourage research by providing a forum for the presentation, exchange, and documentation of relevant information; promote the interaction and communication among its members; and recognize and reward its members for significant contributions to the field of materials science in nuclear technology.
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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
Standards Program
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
Commercial nuclear innovation "new space" age
In early 2006, a start-up company launched a small rocket from a tiny island in the Pacific. It exploded, showering the island with debris. A year later, a second launch attempt sent a rocket to space but failed to make orbit, burning up in the atmosphere. Another year brought a third attempt—and a third failure. The following month, in September 2008, the company used the last of its funds to launch a fourth rocket. It reached orbit, making history as the first privately funded liquid-fueled rocket to do so.
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.