| Titre : | CANDU reactor space-time kinetic model for load following studies (2012) |
| Auteurs : | Lingzhi Xia, Auteur ; Jin Jiang, Auteur |
| Type de document : | Article : texte imprimé |
| Dans : | Transactions of the ASME . Journal of engineering for gas turbines and power (Vol. 133 N° 5, Mai 2011) |
| Article en page(s) : | 09 p. |
| Note générale : | Génie Mécanique |
| Langues : | Anglais |
| Index. décimale : | 620.1 (Essais des matériaux. Défauts des matériaux. Protection des matériaux) |
| Tags : | Fission reactor kinetics Neutron flux |
| Résumé : | This paper presents the development of a three-dimensional space-time neutronic kinetic model of a Canadian deuterium uranium (CANDU) reactor using a modal method. In this method, the reactor space-time neutron flux is synthesized by a time-weighted series of precalculated neutron flux modes. The modes are eigenfunctions of the governing neutron diffusion equation during reference steady-state operation. The xenon effect has also been considered. The reactor model is then implemented within a simulation platform of a CANDU6 reactor regulating system in MATLAB/SIMULINK. A nondimensionalized SIMULINK representation of the reactor kinetic model is established. The behavior of the reactor during load following transients has been simulated using the developed reactor-modeling module. The simulation results prove the efficiency of the model. A three-dimensional neutron flux distribution during transients is represented. |
| DEWEY : | 620.1 |
| ISSN : | 0742-4795 |
| En ligne : | http://scitation.aip.org/getabs/servlet/GetabsServlet?prog=normal&id=JETPEZ000133000005052915000001&idtype=cvips&gifs=Yes&ref=no |
