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Advancing the State of the Practice in Uncertainty and Sensitivity Methodologies for Severe Accident Analysis in Water Cooled Reactors of CANDU Types

Final Report of a Coordinated Research Project


English IAEA-TECDOC-2058 ¦ 978-92-0-122024-0

¦ € 30.00 ¦ Date published: 2024


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The IAEA facilitated collaborative research among its Member States, in advancing the state of the practice in uncertainty and sensitivity methodologies for severe accident analysis in water cooled reactors. The primary aim was to evaluate the uncertainty and sensitivity associated with severe accident calculations, particularly concerning the progression and consequences of accidents in a generic CANDU type nuclear power plant under a postulated station blackout scenario. Key parameters considered in these analyses included hydrogen generation, event timings, and the release of fission products into the environment. The resulting publication showcases contributions from three institutions across three Member States, providing insights into their methodologies for uncertainty and sensitivity analysis in severe accidents.

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Uncertainty Methodologies, Sensitivity Analysis, Severe Accident Analysis, Water Cooled Reactors, CANDU Reactors, Nuclear Power Plant Safety, Accident Progression, Hydrogen Generation, Fission Product Release, Station Blackout Scenario, Severe Accident Calculations, Uncertainty Evaluation, Sensitivity Evaluation, MAAP-CANDU Code, SUSA Code, RELAP/SCDAPSIM Code, CAISER Code, Nuclear Accident Consequences, Member State Collaboration, Nuclear Safety Research, Reactor Safety Parameters

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