Fuel Performance and Thermochemistry Modeling of Candu Nuclear Fuel Progress in Developing a Self Standing Integrated Code

Abstract

A numerical model is in the process of being created to simulate the behaviour of CANDU nuclear fuel under normal operating conditions. A finite volume code is being written in FORTRAN that is capable of predicting heat transfer, fission gas release, grain growth and structural deformation due to: thermal expansion, creep, irradiation-induced densification, fission product swelling and external coolant pressure. A thermodynamic model is also under developmen that is capable of estimating the equilibrium composition of multi-phase and multi-component systems. The coupling of both fuel performance and thermochemistry codes will provide an ideal platform for modeling nuclear fuels under normal and accident conditions.