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Division Spotlight
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.
Meeting Spotlight
Conference on Nuclear Training and Education: A Biennial International Forum (CONTE 2025)
February 3–6, 2025
Amelia Island, FL|Omni Amelia Island Resort
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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December 2024
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November 2024
Latest News
Jeffrey King guides new nuclear program at Tennessee Tech
Jeffrey King
In August, the College of Engineering at Tennessee Technological University welcomed ANS member Jeffrey C. King as the founding director of its new nuclear engineering program. King, a leading force within the American Nuclear Society and a space enthusiast, is tasked with developing a new Department of Nuclear Engineering at Tennessee Tech after a more than 20-year absence of such a program at the university.
King comes to Tennessee Tech from the Colorado School of Mines, where he had been a professor of metallurgical and materials engineering for 15 years, leading the development of the nuclear science and engineering program and serving as director of the Nuclear Science and Engineering Research Center.
Jonathan Scherr, Pavel Tsvetkov
Nuclear Technology | Volume 209 | Number 11 | November 2023 | Pages 1733-1746
Regular Research Article | doi.org/10.1080/00295450.2023.2209229
Articles are hosted by Taylor and Francis Online.
Abilene Christian University (ACU) is developing a 1-MW(thermal) molten salt research reactor that will be built on the ACU campus. A conceptual reactor core model was developed to facilitate the safety analysis required for a construction permit. A series of scoping studies were performed seeking to define the reactor core design parameters subject to a variety of design requirements. A Pareto curve identifying the tradeoff between uranium and LiF-BeF2 was determined. Within this curve, at least 250 kg of uranium and 700 kg of LiF-BeF2 are needed, albeit for different reactor configurations and fuel salt compositions. The cylindrical reactor vessel associated with the best-performing fuel salt composition is ~130 cm in diameter, ~170 cm tall, and contains ~2.5 tons of graphite. The conversion ratio of the reactor is low and will require regular refueling. The shift in neutron spectrum observed with the changing fuel salt composition does not significantly impact reactivity loss with respect to burnup.