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Nuclear Installations Safety
Devoted specifically to the safety of nuclear installations and the health and safety of the public, this division seeks a better understanding of the role of safety in the design, construction and operation of nuclear installation facilities. The division also promotes engineering and scientific technology advancement associated with the safety of such facilities.
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ANS Student Conference 2025
April 3–5, 2025
Albuquerque, NM|The University of New Mexico
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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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Neutron Vision at Los Alamos: Exploring the Frontiers of Nuclear Materials Science
In materials science, understanding the unseen—how materials behave internally under real-world conditions—has always been key to developing new materials and accelerating innovative technologies to market. Moreover, the tools that allow us to see into this invisible world of materials have often been game-changers. Among these, neutron imaging stands out as a uniquely powerful method for investigating the internal structure and behavior of materials without having to alter or destroy the sample. By harnessing the unique properties of neutrons, researchers can uncover the hidden behavior of materials, providing insights essential for advancing nuclear materials and technologies.
Edward Lum, Chad L. Pope
Nuclear Technology | Volume 207 | Number 5 | May 2021 | Pages 761-770
Technical Paper | doi.org/10.1080/00295450.2020.1794190
Articles are hosted by Taylor and Francis Online.
This paper discusses a new method of simulating the fuel assembly duct-bowing reactivity coefficient for EBR-II run 138B. Quantification of the fuel assembly duct-bowing reactivity effect in liquid metal–cooled fast reactors has been a persistent problem since they were first designed and operated. Simulation of the duct-bowing reactivity effect is difficult because the level of detail required to simulate the effect has exceeded most modeling capabilities. The new method outlined in this paper utilizes the finite element analysis code ANSYS to analyze the thermal and structural components. The displacement of the fuel assembly duct due to thermal expansion and mechanical interaction was calculated by ANSYS using recorded EBR-II run 138B temperature and power boundary value data. The displacement values were incorporated into to a Monte Carlo model of EBR-II run 138B and keff was calculated. Multiple Monte Carlo calculations were performed with duct displacement values corresponding to different reactor temperatures. Using the calculated keff values associated with the different duct displacement results allowed calculation of the duct-bowing reactivity coefficient. The duct-bowing reactivity coefficient was calculated to be −14.5 × 10−4 $/°C/ ± 4.4%.