Digital Control System Simulation for Nuclear Reactor Neutronic Parameters

Amir Zacarias Mesquita, Antônio Juscelino Pinto, Clédola Cássia Oliveira de Tello and Fernando Soares Lameiras
Campus da UFMG, Belo Horizonte, MG, Brazil

Series: Physics Research and Technology
BISAC: SCI055000



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Edited by I Leslie Rubin, Robert J Geller, Abby Mutic, Benjamin A Gitterman, Nathan Mutic, Wayne Garfinkel, Claire D Coles, Kurt Martinuzzi, and Joav Merrick


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The International Atomic Energy Agency recommends the use of safety and friendly interfaces for monitoring and controlling the operational parameters of the nuclear reactors. The most important variable in the nuclear reactors control is the power released by fission of the fuel in the core which is directly proportional to neutron flux. It was developed a digital system to simulate the neutron evolution flux and monitoring their interaction on the other operational parameters. The control objective is to bring the reactor power from its source level (mW) to a few W. It is intended for education of basic reactor neutronic principles such as the multiplication factor, criticality, reactivity, period, delayed neutron and control by rods. The 250 kW IPR-R1 TRIGA research reactor at Nuclear Technology Development Center – CDTN (Belo Horizonte/Brazil) was used as reference. (Imprint: Nova)



The IPR-RI Triga Reactor

Triga Nuclear Reactor Kinetics and Control

Digital Instrumentation for Nuclear Reactors

Neutronic Parameters to be Simulated





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