Characterization of the TRIGA Mark II reactor full-power steady state

TL;DR

This paper combines Monte Carlo neutronic simulations with thermal-hydraulics modeling to accurately characterize the full-power steady state of the TRIGA Mark II reactor, validated against experimental data.

Contribution

It introduces a coupled neutronic and thermal-hydraulic modeling approach for reactor steady-state analysis, validated with experimental benchmarks.

Findings

Good agreement with experimental criticality data

Reliable methodology for full-power reactor modeling

Effective coupling of neutronics and thermal-hydraulics

Abstract

In this work, the characterization of the full-power steady state of the TRIGA Mark II nuclear reactor of the University of Pavia is performed by coupling Monte Carlo (MC) simulation for neutronics with "Multiphysics" model for thermal-hydraulics. Neutronic analyses have been performed starting from a MC model of the entire reactor system, based on the MCNP5 code, that was already validated in fresh fuel and zero-power configuration (in which thermal effects are negligible) using the available experimental data as benchmark. In order to describe the full-power reactor configuration, the temperature distribution in the core is necessary. To evaluate it, a thermal-hydraulic model has been developed, using the power distribution results from MC simulation as input. The thermal-hydraulic model is focused on the core active region and takes into account sub-cooled boiling effects present at full reactor power. The obtained temperature distribution is then introduced in the MC model and a benchmark analysis is carried out to validate the model in fresh fuel and full-power configuration. The good agreement between experimental data and simulation results concerning full-power reactor criticality, proves the reliability of the adopted methodology of analysis, both from neutronics and thermal-hydraulics perspective.