Reactor Physics/Neutronic

Energy Research, Inc. has developed multi-dimensional nodal diffusion models for static and dynamic analysis of power reactors, and research reactors. In addition, models have been developed for analysis of a research reactor using the MCNP-CINDER Monte Carlo code.

Combined neutronic and thermal-hydraulic analyses have also been performed for accidents involving main steam line break in PWRs, and anticipated transients without scram for both PWRs and BWRs.