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Conference Spotlight
2026 Nuclear Energy Conference & Expo (NECX)
August 24–27, 2026
Dallas, TX|Hilton Anatole
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Savannah River Site completes concrete work for Saltstone Disposal Unit 11
The Savannah River Site has completed all concrete construction on its “mega-size” Saltstone Disposal Unit (SDU) 11 at the Saltstone Disposal Facility in Aiken, S.C. The several SDUs at the site are designed to provide safe, permanent storage for decontaminated salt solution from the Salt Waste Processing Facility (SWPF) as production is ramped up. The SDUs are crucial components of SRS’s liquid waste program, allowing the site to meet the cleanup responsibilities of the Department of Energy’s Office of Environmental Management.
Kwang-Il Ahn, Federico Mezio, Shaukat Ali, Xuewu Cao, Yong Jin Cho, Bassam Khuwaileh, Victor Martinez-Quiroga, Fulvio Mascari, Fabrizio Gabrielli, David Luxat, Tatjana Jevremovic
Nuclear Technology | Volume 212 | Number 8 | August 2026 | Pages 1879-1905
Research Article | doi.org/10.1080/00295450.2024.2422260
Articles are hosted by Taylor and Francis Online.
In 2019, the International Atomic Energy Agency (IAEA) launched the 5-year Cooperative Research Project (CRP) I31033 to advance the understanding and characterization of sources of uncertainty and to investigate their effects on the key figures of merit (FOMs: response parameters of interest) of the severe accident code predictions for water-cooled reactors. Twenty-two institutions from 18 member states participated in the CRP, and as a result, TECDOCs are being developed for the relevant benchmark exercises. The respective TECDOCs address a specific exercise and outline relevant research results pointing to best practices for the uncertainty and sensitivity analyses of the currently available severe accident codes.
For the uncertainty analysis exercise, the CRP participants defined their own analysis scope and framework, including target plant, severe accident code, accident scenario, and relevant FOMs. According to each respective framework, participants independently carried out their own exercise, including plant modeling and nodalization, simulation of reference cases, and relevant uncertainty and sensitivity analyses.
Finally, general conclusions were made based on an analysis of the results in view of the best-practice application of the uncertainty and sensitivity methods. Among them, this paper summarizes the main results of the uncertainty and sensitivity exercise performed for both pressurized water reactors and integral light water small modular reactors in the frame of the IAEA CRP with relevant insights.