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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.
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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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Fusion Science and Technology
Latest News
A more open future for nuclear research
A growing number of institutional, national, and funder mandates are requiring researchers to make their published work immediately publicly accessible, through either open repositories or open access (OA) publications. In addition, both private and public funders are developing policies, such as those from the Office of Science and Technology Policy and the European Commission, that ask researchers to make publicly available at the time of publication as much of their underlying data and other materials as possible. These, combined with movement in the scientific community toward embracing open science principles (seen, for example, in the dramatic rise of preprint servers like arXiv), demonstrate a need for a different kind of publishing outlet.
E.T. Cheng
Fusion Science and Technology | Volume 39 | Number 2 | March 2001 | Pages 530-534
Nonelectric Applications | doi.org/10.13182/FST01-A11963290
Articles are hosted by Taylor and Francis Online.
An investigation was performed of a flibe blanket to burn actinides extracted from the fission reactor spent fuel. It considered solubility of actinide fluoride in flibe, lithium-6 enrichment, and criticality concerns. Detailed burn-up calculations for a flibe medium containing 0.5 molar percent of actinide isotopes were completed. Performance parameters such as k-eff, tritium breeding ratio, and blanket energy multiplication during burn-up were obtained to assess the characteristics of a flibe based transmutation system. Technical issues associated with use of flibe for burning the transuranic actinides were identified.