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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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2024 ANS Annual Conference
June 16–19, 2024
Las Vegas, NV|Mandalay Bay Resort and Casino
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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
X-energy receives federal tax credit for TRISO fuel facility
Advanced reactor company X-energy has been awarded $148.5 million in tax credits under the Inflation Reduction Act for construction of its TRISO-X fuel fabrication facility in Oak Ridge, Tenn.
U. Fischer, D. Leichtle, A. Serikov, P. Pereslavtsev, R. Villari
Fusion Science and Technology | Volume 64 | Number 3 | September 2013 | Pages 563-570
Nuclear Systems: Analysis and Experiments | Proceedings of the Twentieth Topical Meeting on the Technology of Fusion Energy (TOFE-2012) (Part 2) Nashville, Tennessee, August 27-31, 2012 | doi.org/10.13182/FST13-A19153
Articles are hosted by Taylor and Francis Online.
Several methodologies have been developed for the calculation of shut-down dose rates based on the use of the Monte Carlo (MC) technique for particle transport simulations including the rigorous two-step (R2S) approach and its recent R2Smesh extension, the direct one-step (D1S) method which employs one single MC transport simulation both for neutrons and decay gammas, and a rough rule of thumb (RoT) approximation based on neutron flux-to-dose conversion factors. The paper discusses these approaches and their applications to ITER with focus on dose rate estimations for the equatorial Test Blanket and Diagnostic Ports. These applications are complemented by benchmark analyses on shut-down dose rate measurements performed on JET showing the validity of the R2S and D1S approaches.