Title: User interface for intelligent control schemes in a TRIGA Mark III reactor

Authors: Jorge S. Benitez-Read, Tonatiuh Rivero-Gutierrez, Da Ruan, Cesar L. Ramirez-Chavez, Regulo Lopez-Callejas, Joel O. Pacheco-Sotelo

Addresses: Instituto Nacional de Investigaciones Nucleares (ININ), Carretera Mexico-Toluca S/N, La Marquesa, Ocoyoacac, Mexico, C.P. 52750 and Instituto Tecnologico de Toluca and Fac. de Ing. de la UAEM, Mexico. ' Instituto Nacional de Investigaciones Nucleares (ININ), Carretera Mexico-Toluca S/N, La Marquesa, Ocoyoacac, Mexico, C.P. 52750 and Instituto Tecnologico de Toluca and Fac. de Ing. de la UAEM, Mexico. ' Belgian Nuclear Research Centre (SCK-CEN), Boeretang 200, 2400 Mol, Belgium. ' Instituto Nacional de Investigaciones Nucleares (ININ), Carretera Mexico-Toluca S/N, La Marquesa, Ocoyoacac, Mexico, C.P. 52750 and Instituto Tecnologico de Toluca and Fac. de Ing. de la UAEM, Mexico. ' Instituto Nacional de Investigaciones Nucleares (ININ), Carretera Mexico-Toluca S/N, La Marquesa, Ocoyoacac, Mexico, C.P. 52750 and Instituto Tecnologico de Toluca and Fac. de Ing. de la UAEM, Mexico. ' Instituto Nacional de Investigaciones Nucleares (ININ), Carretera Mexico-Toluca S/N, La Marquesa, Ocoyoacac, Mexico, C.P. 52750 and Instituto Tecnologico de Toluca and Fac. de Ing. de la UAEM, Mexico

Abstract: This paper describes the development of a user interface aimed mainly at testing new power control algorithms in a TRIGA Mark III reactor. The interface is fully compatible with the current computing environment of the reactor|s operating digital console at the Mexican Nuclear Centre. The interface, developed in Visual Basic, has been conceived as an aid tool in the testing and validation of new and existing algorithms for the ascent, regulation and decrease of the reactor power. The design steps of the fuzzy control algorithm for power regulation and the characteristics of the nuclear channels that provide the signals required by the controller are also described in this paper.

Keywords: advanced control; fuzzy control; power control algorithms; nuclear research reactors; simulation; user interfaces; nuclear energy; nuclear power; Mexico; testing; validation; ascent; regulation; decrease; reactor power.

DOI: 10.1504/IJNKM.2007.013563

International Journal of Nuclear Knowledge Management, 2007 Vol.2 No.3, pp.268 - 284

Published online: 06 May 2007 *

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