A MESOSCOPIC OXIDE FUEL CLUSTERING AND ITS GLOBAL PERFORMANCE

Transient fuel behavior in a Light Water-cooled Reactor core depends on nuclear properties (Doppler broadening, moderation ratio, and, sometimes, neutron gas temperature etc.) and variations of thermal-physics parameters (temperature distributions, elongation moderator density). Usually, rough reactor analysis one ignores the very details distributions largely staying frame so-called adiabatic assumptions (when density distribution are changing sync keeping given spatial shapes). In majority practical applications radially distributed fields represented as monotonically smeared ones if fissile other materials homogeneously mixed. Moreover, no measurement technique allows counting precise correlation between reactivity feedback in-pellet space-time distributions. However, is made Mixed Oxide Plutonium-Uranium compound Water would be impacted by an appearance Pu-rich agglomerates that could large enough to change physical processes. such case reacts power more homogeneous but heterogeneous media (on mesoscopic scale, course). It leads changes fission product release even, multiple components Fuel Temperature Coefficient Power Reactivity feedback. These depend non-linearly power, rate some heat transfer. This paper only first step broad research program where we estimating relevant phenomena just order magnitude.