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Conference Spotlight
Nuclear Energy Conference & Expo (NECX)
September 8–11, 2025
Atlanta, GA|Atlanta Marriott Marquis
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
The value of recycled U and Pu brings Standard Nuclear and Shine together
Shine Technologies has been developing fusion-adjacent technologies in Janesville, Wis., including nuclear fuel recycling, since its founding in 2005. Standard Nuclear of Oak Ridge, Tenn., was formed just last year but holds a TRISO fuel production technology backed by years of research and development since it acquired Ultra Safe Nuclear’s fuel manufacturing assets after that company’s bankruptcy in October 2024. Now, Shine and Standard Nuclear have announced plans to work together on a “strategic partnership to advance nuclear fuel recycling and U.S. fuel security.”
Aaron J. Reynolds, Todd S. Palmer
Nuclear Science and Engineering | Volume 197 | Number 1 | January 2023 | Pages 45-73
Technical Paper | doi.org/10.1080/00295639.2022.2097565
Articles are hosted by Taylor and Francis Online.
We use the deterministic neutron transport code QuasiMolto to simulate steady-state operation of the Molten Salt Reactor Experiment (MSRE). Comparisons are made to similar results from the MOST benchmark, the MOOSE-based code Moltres, and the design calculations for the MSRE. In the course of these comparisons, we calculate a value of 0.1799 for the graphite-to-fuel power density ratio, which differs significantly from that seen in other works. We also find uniform graphite heating inadequate to reproduce the characteristic graphite temperature distribution of the MSRE. Leveraging the multilevel projective methodology of QuasiMolto, the influence of transport effects on the modeled problem is found to produce average and maximum group flux variations of 2% to 5% and 30%, respectively, with a 12% variation in the reactivity loss due to delayed neutron precursor drift.