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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
Utility Working Conference and Vendor Technology Expo (UWC 2024)
August 4–7, 2024
Marco Island, FL|JW Marriott Marco Island
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
Taking shape: Fusion energy ecosystems built with public-private partnerships
It’s possible to describe fusion in simple terms: heat and squeeze small atoms to get abundant clean energy. But there’s nothing simple about getting fusion ready for the grid.
Private developers, national lab and university researchers, suppliers, and end users working toward that goal are developing a range of complex technologies to reach fusion temperatures and pressures, confounded by science and technology gaps linked to plasma behavior; materials, diagnostics, and electronics for extreme environments; fuel cycle sustainability; and economics.
Tomohiro Endo, Akio Yamamoto
Nuclear Science and Engineering | Volume 194 | Number 11 | November 2020 | Pages 1089-1104
Technical Paper | doi.org/10.1080/00295639.2020.1720499
Articles are hosted by Taylor and Francis Online.
The prompt neutron decay constant in a steady-state subcritical system can be directly measured using a reactor noise analysis method such as the Feynman- method. To reduce the nuclear data–induced uncertainty of for a target system, this study investigates the applicability of data assimilation techniques, i.e., the bias factor method and the cross-section adjustment method, based on a subcritical measurement of conducted at Kyoto University Critical Assembly (KUCA). The sensitivity coefficients of and with respect to the nuclear data were efficiently estimated using a deterministic SN transport code with first-order perturbation theory. As a result, the a priori relative uncertainty of due to the 56-group SCALE covariance data can be reduced if there is strong correlation between the measured and the target . The experimental value of contributes to improving the nuclear data of total fission spectrum and total fission neutron number via strong correlations between and prompt and between and prompt , by utilizing the sensitivity coefficients of with respect to prompt and .