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Conference Spotlight
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.
Workshop
Thursday, April 8, 2021|11:45AM–1:00PM EDT
Session Chair:
Mihai A. Diaconeasa
Alternate Chair:
Arjun Earthperson (NC State Univ.)
Session Organizer:
Edward Chen (NC State Univ.)
Track Organizer:
Session Producers:
Alp Tezbasaran (NCSU)
How safe is safe enough? Probabilistic Risk Assessment (PRA), also called Quantitative Risk Assessment (QRA), has been very effective in supporting better decisions on how to manage safety by making the risks involved, the contributors, and the options for controlling the risk transparent; and, quantifying the uncertainties, the primary contributor to rare event risk. Moreover, a new generation of methodologies, often referred to as Dynamic PRA (DPRA) or simulation-based PRA, is starting to receive attention for nuclear reactor PRA. These methodologies explicitly account for the time element in the probabilistic system evolution, quantify the effects of phenomenological variability and uncertainties, and are driven by plant analysis tools (e.g., RELAP, MAAP5) to model possible dependencies among failure events that may arise from hardware/software/human interactions. They have shown great promise in reducing user-to-user analysis variability, modeling passive safety systems, aging effects, and human performance. This workshop will cover the principles of PRA, hands-on examples, as well as brief reviews of recent developments in simulation-based PRA methodologies.
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