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August 24–27, 2026
Dallas, TX|Hilton Anatole
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Spent fuel recycling and conditioning topic of U.S.-Japan meeting
Officials with the Department of Energy’s Office of Environmental Management discussed spent nuclear fuel recycling and conditioning with counterparts from Japan during the 13th U.S.-Japan Technical Meeting of the Civil Nuclear Energy Research and Development Working Group, held recently in Santa Fe, N.M.
Noel B. Nelson, Andrew J. Conant, Jorge Navarro, Robert N. Wahlen, Chad P. Denbrock, Terry L. Grimm
Nuclear Science and Engineering | Volume 200 | Number 7 | July 2026 | Pages 1651-1672
Research Article | doi.org/10.1080/00295639.2025.2540659
Articles are hosted by Taylor and Francis Online.
Commonly produced as a byproduct of uranium fission, 99Mo is a key medical isotope that is in high demand in the United States. An international goal is to switch from medical isotope production technologies that require highly enriched uranium to medical isotope production technologies that require only low-enriched uranium. Niowave Inc. is contributing to this goal by developing an accelerator-driven subcritical assembly called the Uranium Target Assembly (UTA). This work compares the performance of Dakota’s Multi-Objective Genetic Algorithm (MOGA) against traditional sensitivity analysis in the neutronic optimization of the UTA-3 system. The design objectives are k-eigenvalue (keff) and natural uranium fission power, which are directly correlated with the amount of 99Mo produced. Dakota:MOGA did not perform as well as human engineering ingenuity in optimization studies with high numbers of input parameters, such as fuel rod type selection and fuel rod placement. However, Dakota:MOGA did outperform traditional sensitivity analysis in optimization studies with fewer than 20 parameters and revealed the degree to which each parameter influences the optimal design space for keff and natural uranium fission power (to a lesser extent). As the design model became more complex in the final stage of design, the computational resources required to calculate the design objective values in the Monte Carlo N-Particle transport code from selected input parameter combinations limited Dakota:MOGA’s performance, and, unfortunately, human intervention was required to discern the optimal design space. Future work will attempt to reduce computational resource constraints by incorporating areduced-order neutronics model into the optimization cycle.