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2026 ANS Annual Conference
May 31–June 3, 2026
Denver, CO|Sheraton Denver
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AI at work: Southern Nuclear’s adoption of Copilot agents drives fleet forward
Southern Nuclear is leading the charge in artificial intelligence integration, with employee-developed applications driving efficiencies in maintenance, operations, safety, and performance.
The tools span all roles within the company, with thousands of documented uses throughout the fleet, including improved maintenance efficiency, risk awareness in maintenance activities, and better-informed decision-making. The data-intensive process of preparing for and executing maintenance operations is streamlined by leveraging AI to put the right information at the fingertips for maintenance leaders, planners, schedulers, engineers, and technicians.
M. K. Sheaffer, M. J. Driscoll, I. Kaplan
Nuclear Science and Engineering | Volume 48 | Number 4 | August 1972 | Pages 459-466
Technical Paper | doi.org/10.13182/NSE72-A22513
Articles are hosted by Taylor and Francis Online.
A one-group method for the calculation of neutron balances in fast reactor cores is developed and evaluated. The key feature of the method is the definition of two spectrum characterization parameters in terms of spectrum-averaged one-group cross sections for the homogenized core composition: where ξel is the mean logarithmic energy decrement for elastic moderation and ∑f, ∑TR, and are fission, transport, and removal cross sections, respectively. All required cross sections can then be correlated in the form = σ1 Sg (where and g are constants; one pair of values correlated for each cross section) except for threshold fission for which = σ1Rg. A rapidly converging iterative procedure is presented through which S and R can be determined for any core composition. Microscopic cross-section data are correlated in the above form using the 26-group ABBN multigroup set as parent data. The one-group method is tested for 45 different fast reactor core compositions by comparing the results of the one-group calculations with those of 26-group calculations. The results are found to agree within an average error of ±1.77% in the material buckling or to ±0.69% in effective multiplication factor. One-group relationships are also developed for the calculation ofprompt-neutron lifetime, Doppler reactivity, and other parameters of interest.
