ANS is committed to advancing, fostering, and promoting the development and application of nuclear sciences and technologies to benefit society.
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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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Latest News
US, Korea sign MOU for nuclear cooperation
The U.S. departments of Energy and State have signed a memorandum of understanding with the Republic of Korea’s ministries of Trade, Industry and Energy and of Foreign Affairs for the two nations to partner on nuclear exports and cooperation.
Anton Moisseytsev, Matthew Bucknor, James J. Sienicki
Nuclear Science and Engineering | Volume 196 | Number 1 | October 2022 | Pages S323-S336
Technical Paper | doi.org/10.1080/00295639.2021.2018925
Articles are hosted by Taylor and Francis Online.
Because the Versatile Test Reactor (VTR) uses sodium as a primary and secondary coolant, an analysis of postulated sodium leaks that could result in sodium fires is needed for VTR safety analysis. The goals of such an analysis include, among other topics, determination of temperature and pressure loadings on the reactor building from sodium fires. This paper provides a description of sodium spray and pool fire analysis tool development at Argonne National Laboratory for application to the VTR and includes validation against available data from sodium fire experiments.
