A Dynamic Simulation Tool For Critical Assemblies Using The Coupled Neutronic-thermoelastic Method

摘要

The enhanced MRKJ code uses a coupled neutronic-thermoelastic model that can be used to simulate the dynamic behavior of critical assemblies, pulse research reactors, and other nuclear systems. Both the thermal and mechanical behavior of fuel-bearing materials is simulated during excursions. The code can be utilized to provide initial estimates for criticality accident consequence analysis or prototype nuclear dynamic performance.