This work is based on an object-oriented approach for the modeling and simulation of the reactor dynamics. The model is applied and validated on a TRIGA Mark II reactor. The aim of this work is to investigate the neutronic reactivity model, accounting for the temperature feedback of the fuel and of the moderator, as well as the poisons accumulation effects. The reactivity model is validated on experimental data from extended transients of the system temperature, at nominal power. In particular, the positive value of moderator temperature coefficient and the negative value of fuel temperature coefficient are estimated at nominal power. There is good agreement of the extended experimental transients with the whole reactivity and thermodynamics model of the plant. The model simulation shows a good reliability against experimental data and a good trade-off to computational time. In the extended transients, the model tracks the effects of the reactor pool thermal inertia on the system dynamics.

Setting-up a control-oriented model for simulation of TRIGA Mark II dynamic response

Boarin, S.;Cammi, A.;Ricotti, M. E.;
2018-01-01

Abstract

This work is based on an object-oriented approach for the modeling and simulation of the reactor dynamics. The model is applied and validated on a TRIGA Mark II reactor. The aim of this work is to investigate the neutronic reactivity model, accounting for the temperature feedback of the fuel and of the moderator, as well as the poisons accumulation effects. The reactivity model is validated on experimental data from extended transients of the system temperature, at nominal power. In particular, the positive value of moderator temperature coefficient and the negative value of fuel temperature coefficient are estimated at nominal power. There is good agreement of the extended experimental transients with the whole reactivity and thermodynamics model of the plant. The model simulation shows a good reliability against experimental data and a good trade-off to computational time. In the extended transients, the model tracks the effects of the reactor pool thermal inertia on the system dynamics.
2018
Dymola model; Moderator coefficient; Reactivity feedback; Transient simulation; TRIGA Mark II; Nuclear and High Energy Physics; Nuclear Energy and Engineering; Materials Science (all); Safety, Risk, Reliability and Quality; Waste Management and Disposal; Mechanical Engineering
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Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/11311/1127477
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