APPLICATION OF RESPONSE MATRIX METHOD TO TRANSIENT SIMULATIONS OF NUCLEAR SYSTEMS

Until recently, reactor transient problems were exclusively solved by approximate deterministic methods. The increase in available computing power made it feasible to approach the analyses with time-dependent Monte Carlo These methods offer first-principle solution space-time evolution of explicitly tracking prompt neutrons, precursors delayed neutrons and time space. Nevertheless, a very significant cost is associated such general benefits may be retained at reduced applying hybrid stochastic-deterministic scheme. Among schemes are those based on fission matrix response formalisms. aim estimating variant Greens function during transport calculation, which later used formulate solving dependent problem. In this contribution, we provide an overview method, describes system set functions. We have recently suggested where functions determined criticality calculation then deterministically solve behaviour system. Here, compare solutions for control rod movement problem mini-core geometry. formalism results loosely connected equations offers favourable scaling properties compared formalism.