Aim of this work is to reproduce the dynamic behavior of the TRIGA Mark II reactor of the University of Pavia on the entire operative power range (i.e. 0e250 kW) using a zero dimensional approach. In this work the coupling between neutronics and thermal-hydraulics in natural circulation has been considered. In specific, a point reactor kinetics model with one energy group and six delayed neutron precursors groups has been adopted while for thermal-hydraulics modeling two regions have been defined (i.e. the fuel and the coolant). The nonlinear system of coupled Ordinary Differential Equations has been solved by means of MATLAB Simulink, which represents a reliable tool for dynamic and control analysis. The model has then been validated through the comparison with a set of experimental data collected in four different reactor power transients, obtaining a very satisfying agreement. Finally, the linear stability analysis of the TRIGA reactor has been performed by means of the root locus, finding out that the power level at which reactor is operating deeply influences the position of the poles of the transfer function between control rod height and neutron density. These results can then be employed as a reliable starting point in designing an automatic device for reactor power control.

A zero dimensional model for simulation of TRIGA Mark II dynamic response

BORIO DI TIGLIOLE, ANDREA;MAGROTTI, GIOVANNI;PRATA, MICHELE;CHIESA, DAVIDE;
2013-01-01

Abstract

Aim of this work is to reproduce the dynamic behavior of the TRIGA Mark II reactor of the University of Pavia on the entire operative power range (i.e. 0e250 kW) using a zero dimensional approach. In this work the coupling between neutronics and thermal-hydraulics in natural circulation has been considered. In specific, a point reactor kinetics model with one energy group and six delayed neutron precursors groups has been adopted while for thermal-hydraulics modeling two regions have been defined (i.e. the fuel and the coolant). The nonlinear system of coupled Ordinary Differential Equations has been solved by means of MATLAB Simulink, which represents a reliable tool for dynamic and control analysis. The model has then been validated through the comparison with a set of experimental data collected in four different reactor power transients, obtaining a very satisfying agreement. Finally, the linear stability analysis of the TRIGA reactor has been performed by means of the root locus, finding out that the power level at which reactor is operating deeply influences the position of the poles of the transfer function between control rod height and neutron density. These results can then be employed as a reliable starting point in designing an automatic device for reactor power control.
2013
Nuclear Engineering covers resources concerned with the branch of engineering that deals with the production and use of nuclear energy, including the development, design, construction, and operation of power plants that convert energy produced by fission or fusion to other useful forms of energy such as heat and light.
no
Esperti anonimi
Inglese
Internazionale
STAMPA
68
43
54
12
Dynamic system response; Modeling; Root locus method; TRIGA reactor; Energy Engineering and Power Technology; Nuclear Energy and Engineering; Waste Management and Disposal; Safety, Risk, Reliability and Quality
http://dx.doi.org/10.1016/j.pnucene.2013.04.002
no
7
info:eu-repo/semantics/article
262
Cammi, Antonio; Ponciroli, Roberto; BORIO DI TIGLIOLE, Andrea; Magrotti, Giovanni; Prata, Michele; Chiesa, Davide; Previtali, Ezio
1 Contributo su Rivista::1.1 Articolo in rivista
none
File in questo prodotto:
Non ci sono file associati a questo prodotto.

I documenti in IRIS sono protetti da copyright e tutti i diritti sono riservati, salvo diversa indicazione.

Utilizza questo identificativo per citare o creare un link a questo documento: https://hdl.handle.net/11571/1160342
Citazioni
  • ???jsp.display-item.citation.pmc??? ND
  • Scopus 24
  • ???jsp.display-item.citation.isi??? ND
social impact