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2026 Nuclear Energy Conference & Expo (NECX)
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.
Yuehang Li, Donghao He, Xiaojing Liu, Qingquan Pan
Nuclear Science and Engineering | Volume 200 | Number 5 | May 2026 | Pages 1118-1135
Research Article | doi.org/10.1080/00295639.2025.2510708
Articles are hosted by Taylor and Francis Online.
The Transient Fission Matrix Combination (TFMC) method is a novel hybrid algorithm that performs transient neutron transport calculations with high fidelity and computational efficiency. In this paper, we verify the TFMC method using the control rod insertion/withdrawal C5G7-TD benchmark. The TD4 test case involves five complex control rod movement patterns in a four-assembly light water reactor model. On 20 parallel cores, each 16-s transient simulation completes in approximately 2 min (excluding database generation time). The computed total power and power distributions agree closely with reference results in all cases. These findings demonstrate the TFMC method’s potential as an efficient and accurate tool for transient neutron transport simulations.