An Iterative Method for Simulation of Dynamic Behavior in Fast Burst Reactors

摘要

Initial runs met with surprising success given the preliminary nature of the method employed (a coupling between two established software tools, instead of creation and use of an integrated tool). However, other than the unusual thermomechanical behavior observed in SPRIII, the reactor is remarkably simple to model: point kinetics equations are valid, delayed neutrons may be ignored, and the geometry and material data are treatable in one spatial dimension. All these assumptions fail in nuclear assemblies of more common design. A great deal of work remains to generalize to solutions on more complicated geometries involving more than one set of material data. The goal is general mathematical modeling of time-dependent behavior in systems where thermomechanical displacement plays a significant role in criticality changes.