Preliminary Modeling and Analysis Framework for Severe Accident Analysis of High Power Density Research Reactors.

摘要

Recent studies of research and production reactor safety are prompting the need for extended severe accident analysis capabilities for those facilities. High power density research reactors have unique design and safety features, and a program to address severe accident issues in such reactors was recently initiated at the Oak Ridge National Laboratory (ORNL). The phased approach and methodology proposed to address severe accident issues in high power density research reactors are presented, along with some emerging insights from ORNL's severe accident studies for the 85 MWt High Flux Isotope Reactor (HFIR) and the planned 332 MWt Advanced Neutron Source (ANS). The goal of these efforts is to provide a more detailed and credible simulation of severe accident issues for research reactors, such as core melting and relocation, fuel-coolant interactions, and core-concrete interactions, than is possible via application of the current generation of light water reactor (LWR) severe accident analysis codes. 3 refs., 2 tabs.