Sensitivity analysis and uncertainty quantification in PWR irradiation ageing like problems
Résumé
The lifespan of nuclear power plants is a critical aspect
of energy production, with reactor vessel ageing being one of
the main challenges. Over time, ageing under neutron
irradiation of the Pressurized Water Reactor (PWR) vessels
leads to changes in the material's micro-structure. These
changes adversely affect the mechanical properties, making
the material more brittle and susceptible to fractures,
especially under strong temperature gradients. Beyond the
vessel, the aging of other elements, such as concrete
structures, also poses significant concerns. Accurate
calculations of neutron fluence and the associated
uncertainties throughout and beyond the reactor vessel are
essential to ensure safety. This study aims at addressing this
issue by applying a specific methodology to a simplified
model, providing a foundational step to quantify the
uncertainty in Monte-Carlo simulations related to irradiation
ageing in nuclear reactors.
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