In this paper, the characterization of the full-power steady state of the TRIGA Mark II nuclear reactor at the University of Pavia is achieved by coupling the Monte Carlo (MC) simulation for neutronics with the "Multiphysics" model for thermal-hydraulics. Neutronic analyses have been carried out with a MCNP5 based MC model of the entire reactor system, already validated in fresh fuel and zero-power configurations (in which thermal effects are negligible) and using all available experimental data as a benchmark. In order to describe the full-power reactor configuration, the temperature distribution in the core must be established. To evaluate this, a thermal-hydraulic model has been developed, using the power distribution results from the 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 entered into the MC model and a benchmark analysis is carried out to validate the model in fresh fuel and full-power configurations. An acceptable correspondence between experimental data and simulation results concerning full-power reactor criticality proves the reliability of the adopted methodology of analysis, both from the perspective of neutronics and thermal-hydraulics.

Cammi, A., Zanetti, M., Chiesa, D., Clemenza, M., Pozzi, S., Previtali, E., et al. (2016). Characterization of the TRIGA Mark II reactor full-power steady state. NUCLEAR ENGINEERING AND DESIGN, 300, 308-321 [10.1016/j.nucengdes.2016.01.026].

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

CHIESA, DAVIDE;CLEMENZA, MASSIMILIANO;POZZI, STEFANO;PREVITALI, EZIO;SISTI, MONICA;
2016

Abstract

In this paper, the characterization of the full-power steady state of the TRIGA Mark II nuclear reactor at the University of Pavia is achieved by coupling the Monte Carlo (MC) simulation for neutronics with the "Multiphysics" model for thermal-hydraulics. Neutronic analyses have been carried out with a MCNP5 based MC model of the entire reactor system, already validated in fresh fuel and zero-power configurations (in which thermal effects are negligible) and using all available experimental data as a benchmark. In order to describe the full-power reactor configuration, the temperature distribution in the core must be established. To evaluate this, a thermal-hydraulic model has been developed, using the power distribution results from the 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 entered into the MC model and a benchmark analysis is carried out to validate the model in fresh fuel and full-power configurations. An acceptable correspondence between experimental data and simulation results concerning full-power reactor criticality proves the reliability of the adopted methodology of analysis, both from the perspective of neutronics and thermal-hydraulics.
Articolo in rivista - Articolo scientifico
Hydraulic models; Hydraulics; Nuclear reactors; Reliability analysis; Temperature distribution; Benchmark analysis; Neutronic analysis; Power configuration; Power distributions; Reactor systems; Sub-cooled boiling; Thermal hydraulic modeling; Thermal hydraulics; Monte Carlo methods;
English
308
321
14
Cammi, A., Zanetti, M., Chiesa, D., Clemenza, M., Pozzi, S., Previtali, E., et al. (2016). Characterization of the TRIGA Mark II reactor full-power steady state. NUCLEAR ENGINEERING AND DESIGN, 300, 308-321 [10.1016/j.nucengdes.2016.01.026].
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/10281/120909
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