  In nuclear engineering studies, uncertainty and sensitivity analyses of
simulation computer codes can be faced to the complexity of the input and/or
the output variables. If these variables represent a transient or a spatial
phenomenon, the difficulty is to provide tool adapted to their functional
nature. In this paper, we describe useful visualization tools in the context of
uncertainty analysis of model transient outputs. Our application involves
thermal-hydraulic computations for safety studies of nuclear pressurized water
reactors.
