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The division's objectives are to promote the advancement of knowledge and understanding of the fundamental physical phenomena characterizing nuclear reactors and other nuclear systems. The division encourages research and disseminates information through meetings and publications. Areas of technical interest include nuclear data, particle interactions and transport, reactor and nuclear systems analysis, methods, design, validation and operating experience and standards. The Wigner Award heads the awards program.
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2025 ANS Annual Conference
June 15–18, 2025
Chicago, IL|Chicago Marriott Downtown
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Smarter waste strategies: Helping deliver on the promise of advanced nuclear
At COP28, held in Dubai in 2023, a clear consensus emerged: Nuclear energy must be a cornerstone of the global clean energy transition. With electricity demand projected to soar as we decarbonize not just power but also industry, transport, and heat, the case for new nuclear is compelling. More than 20 countries committed to tripling global nuclear capacity by 2050. In the United States alone, the Department of Energy forecasts that the country’s current nuclear capacity could more than triple, adding 200 GW of new nuclear to the existing 95 GW by mid-century.
M. Z. Youssef, A. Kumar, M. Abdou, M. Nakagawa, K. Kosako, Y. Oyama, T. Nakamura
Fusion Science and Technology | Volume 19 | Number 3 | May 1991 | Pages 1891-1902
Neutronic | Proceedings of the Ninth Topical Meeting on the Technology of Fusion Energy (Oak Brook, Illinois, October 7-11, 1990) | doi.org/10.13182/FST91-A29619
Articles are hosted by Taylor and Francis Online.
Effort in Phase IIC of the US/JAERI Collaborative Program on Fusion Neutronics was focused on performing integral experiments and post analyses on blankets that include the actual hetergeneities found in several blanket designs. Two geometrical arrangements were considered, namely multilayers of Li2O and beryllium in an edge-on, horizontally alternating configuration for a front depth of 30 cm, followed by the Li2O breeding zone (Be edge-on, BEO, experiment), and vertical water coolant channels arrangement in which one is placed behind the first wall and two other channels (width of 0.5 cm each) are placed at depths of 10 and 30 cm from the first wall (WCC experiment). The objectives are to experimentally verify the enhancement in tritium production in the first experiment and to examine the accuracy of predicting tritium production and other reaction rates around these heterogeneities in the two experiments. In the BOE system, it was shown that, with the zonal method to measure tritium production from natural lithium (Tn), the calculated-to-measured values (C/E) are 0.95 − 1.05 (JAERI) and 0.98 − 0.9 (U.S.), which is consistent with the results obtained in other Phases of the Program. In the WCC experiment, there is a noticeable change in C/E values for T6 near the coolant channels where steep gradients in T6 production are observed. The C/E values obtained with the Li-foils to measure T6 are better than those obtained by the Li-glass method. As for T7, calculations and measurements by NE213 method are within ± 15% in JAERI's analysis, but larger values (∼ 20–25%) are obtained in the U.S. analysis. Around heterogeneities, the prediction accuracy for T7 is better than that for T6. In both experiments, the prediction accuracy for high-threshold reactions [(e.g. 93Nb(n,2n)] is within ± 10% as obtained by both Monte Carlo and Sn codes, however, it was shown that the 58Ni(n,2n) cross-section of ENDF/B-V should be increased by 25–30% at high incident neutron energies to give better C/E values.