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Division Spotlight
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.
Meeting Spotlight
ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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
El Salvador: Looking to nuclear
In 2022, El Salvador’s leadership decided to expand its modest, mostly hydro- and geothermal-based electricity system, which is supported by expensive imported natural gas and diesel generation. They chose to use advanced nuclear reactors, preferably fueled by thorium-based fuels, to power their civilian efforts. The choice of thorium was made to inform the world that the reactor program was for civilian purposes only, and so they chose a fuel that was plentiful, easy to source and work with, and not a proliferation risk.
Xiangyun Zhou, Annan Zhou, De’An Sun, Daichao Sheng
Nuclear Technology | Volume 207 | Number 2 | February 2021 | Pages 247-262
Technical Paper | doi.org/10.1080/00295450.2020.1756161
Articles are hosted by Taylor and Francis Online.
The temperature field in a nuclear waste repository is an important issue with regard to the design and safety assessment of the repository. In this paper, a double-layer model for simulating the heat conduction near a single waste canister is established, and then, by applying the Laplace transform to the governing equations of the heat conduction in the buffer layer and the surrounding rock, the solutions of the temperature field are obtained in the Laplace domain. The temperature distribution near the nuclear waste canister is presented by numerical inversion of the solutions using Crump’s method in the time-space domain. Finally, the effects of parameters on the temperature on the canister surface are analyzed. The results show that the double-layer model of the heat conduction increases the maximum temperature on the canister surface by about 11.87°C compared to the single-layer model. The double-layer model is verified to be reliable by comparing with a line heat source model that has been verified by numerical calculations. The temperature on the canister surface is significantly affected by the burnup value and cooling time of the nuclear waste, the thickness of the buffer layer, the thermal conductivities of the buffer material and the surrounding rock, and the external boundary condition.