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Mathematics & Computation
Division members promote the advancement of mathematical and computational methods for solving problems arising in all disciplines encompassed by the Society. They place particular emphasis on numerical techniques for efficient computer applications to aid in the dissemination, integration, and proper use of computer codes, including preparation of computational benchmark and development of standards for computing practices, and to encourage the development on new computer codes and broaden their use.
2021 ANS Winter Meeting and Technology Expo
November 30–December 3, 2021
Washington, DC|Washington Hilton
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Nuclear Science and Engineering
Fusion Science and Technology
Ensuring a role for nuclear in the response to climate change
Nuclear power is an important tool in the response to climate change, and advanced reactors may offer advantages over existing plants in providing carbon-free generation at the scale necessary to respond to the existential challenge that climate change presents. The International Atomic Energy Agency is aggressively addressing issues related to the possible transition to advanced reactors. This letter is to urge a redoubling of effort by Member States to put in place the necessary capabilities to deal with the challenges that they present.
Gary M. Stange, Michael Corradini, Robert Swader, George Petry, Thomas R. Mackie, Kevin W. Eliceiri
Nuclear Technology | Volume 197 | Number 2 | February 2017 | Pages 191-200
Technical Paper | dx.doi.org/10.13182/NT16-107
Articles are hosted by Taylor and Francis Online.
Uranyl nitrate hexahydrate [UO2(NO3)2 · 6H2O] (UNH) holds interest as a potential nuclear reactor fuel for manufacturing the key medical isotope 99mTc through the production and subsequent decay of 99Mo. Fuel element design for such a production method requires knowledge of the thermal properties of the fuel material, particularly in the case of UNH, which has a significantly lower melting temperature than that of fuels being used currently. A system was designed to measure the thermal conductivity of UNH by an ASTM International standard thermal probe method. Measurements were made at four temperatures within the relevant range for the reactor system (25°C through 55°C) and with a variety of material preparations. With a fill gas of air, the results demonstrate a thermal conductivity at 25°C between 0.07 and 0.10 W · cm−1 · K−1. The results are the first step toward future studies that could lead to a more efficient reactor design with a heating source term capable of meeting the demand for 99Mo production while maintaining a safe and effective thermal margin.