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Nuclear Criticality Safety
NCSD provides communication among nuclear criticality safety professionals through the development of standards, the evolution of training methods and materials, the presentation of technical data and procedures, and the creation of specialty publications. In these ways, the division furthers the exchange of technical information on nuclear criticality safety with the ultimate goal of promoting the safe handling of fissionable materials outside reactors.
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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
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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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Christmas Night
Twas the night before Christmas when all through the houseNo electrons were flowing through even my mouse.
All devices were plugged in by the chimney with careWith the hope that St. Nikola Tesla would share.
Woong Heo, Yonghee Kim
Nuclear Science and Engineering | Volume 189 | Number 1 | January 2018 | Pages 41-55
Technical Paper | doi.org/10.1080/00295639.2017.1373516
Articles are hosted by Taylor and Francis Online.
Thermomechanical effects, irradiation, and structural restrictions result in very tangled behavior of assemblies in sodium-cooled fast reactors (SFRs). Reactivity feedback caused by the assembly behavior (deformation or distortion) is one of the key parameters in the inherent safety analysis of fast reactor systems. However, to date there has been no accurate and efficient deterministic way to compute directly the reactivity changes by actual local perturbation. This paper evaluates the feasibility of applying the Galerkin finite element method (GFEM) based on linear shape functions to estimate reactivity changes due to local core deformations in SFRs. Assessment of reactivity changes is conducted for six types of deformation scenarios of the two-dimensional prototype Gen-IV SFR. Uniform expansions and local deformations are included in the scenarios. The results from the multigroup diffusion equation based on the GFEM are compared with references calculated by MCNP5. The study shows that diffusion analysis based on the GFEM with linear shape functions can properly estimate reactivity changes by core deformation in the fast reactor with ~13% relative error of Δρ.