Coupled neutronics / thermal hydraulics calculations for High Temperature Reactors with the DALTON - THERMIX code system

摘要

A code system for the simulation of steady state and transient behavior of High Temperature Pebble-Bed type Reactors was developed. To this end a new time-dependent (3D) diffusion code DALTON was coupled to an existing thermal-hydraulics code THERMIX.In order to validate the code system, simulations of the Pebble Bed Modular Reactor (PBMR) design and the Arbeitsgemeinschaft Versuchsreaktor (AVR) were performed for steady state and transient conditions. Special attention has gone to the coupled calculation methodology for the various types of transients.Both the PBMR simulations and a comparison of the calculation results with experimental data of the AVR were satisfactory. The code system provides a key element in the development and optimization of (Very) High Temperature Reactor designs in the framework of the RAPHAEL project.