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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
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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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Retrieval of nuclear waste canisters from a borehole
Borehole disposal of spent nuclear fuel (SNF) and high-level waste (HLW) uses off-the-shelf directional drilling technology developed and commercialized by the oil and gas sectors. It is a technology that has been gaining traction in recent years in the nuclear industry. Disposal can be done in one or more boreholes (including an array) drilled into suitable sedimentary, igneous, or metamorphic host rocks. Waste is encapsulated in specialized corrosion-resistant canisters, which are placed end to end in disposal sections of relatively small-diameter boreholes that have been cased and fluid-filled. After emplacement, the vertical access hole is plugged and backfilled as an engineered barrier.
Gyoo Won Suh and Hee Cheon No
Nuclear Science and Engineering | Volume 90 | Number 3 | July 1985 | Pages 236-247
Technical Paper | doi.org/10.13182/NSE85-A17765
Articles are hosted by Taylor and Francis Online.
The USODA (U-tube Steam Generator Controller Design Analysis) code was developed to simulate the transient behavior of a vertical natural circulation U-tube steam generator in pressurized water reactors and to design the optimal level controller. The steam generator was represented by sixth order linear differential equations through matrix reduction. The momentum equation for the recirculation flow models the effects of the separators, U-bend regions, and spatial acceleration. To assure stability, the Lyapunov theorem was adopted. The optimal gains were obtained by minimizing the quadratic performance index and by using both Newton-Raphson and successive overrelaxation methods, which guarantee fast convergence. Sample calculations for Korea Nuclear Unit 2 showed that a control system consisting of standard proportional integral differential controls can be successfully employed for the control of water level. The optimization procedure led to a stable system with good controlled response.