Design of a digital system for operational parameters simulation of IPR-R1 Triga nuclear research reactor

Authors

  • Aldo Márcio Fonseca Lage Centro de Desenvolvimento da Tecnologia Nuclear - CDTN
  • Adriano Almeida Massaud Felippe Universidade Federal de Minas Gerais (UFMG)
  • Amir Zacarias Mesquita Centro de Desenvolvimento da Tecnologia Nuclear (CDTN/Cnen-MG)

DOI:

https://doi.org/10.15392/bjrs.v7i2B.691

Keywords:

Simulation, modeling, nuclear reactor

Abstract

The instrumentation of nuclear reactors is designed based on the reliability, redundancy and diversification of control systems. The monitoring of the parameters is of crucial importance with regard to the operational efficiency and safety of the installation. Since the first criticality of a nuclear reactor, achieved by Fermi et al. in 1942, there has been concern about the reliable monitoring of the parameters involved in the chain reaction. This paper presents the current stage of the system of simulation, which is under development at the CDTN, which intends to simulate the operation of the Triga IPR-R1 nuclear reactor, involving the evolution of neutron flux and reactor power related events. The system will be developed using LabVIEW® software, using the modern concept of virtual instruments (VIs) that are visualized in a video monitor. For the implementation of this model, computational tools and systems analysis are necessary, which help and facilitate the implementation of the simulator. In this article we will show some of these techniques and the initial design of the model to be implemented. The design of a computational system is of great importance, since it guides in the implementation stages and generates the documentation for later maintenance and updating of the computational system. It is noteworthy that the innovations developed in research reactors are normally used in power reactors. The relatively low costs enable research reactors to be an excellent laboratory for developing techniques for future reactors.

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Author Biography

Aldo Márcio Fonseca Lage, Centro de Desenvolvimento da Tecnologia Nuclear - CDTN

Av. Presidente Antônio Carlos, 6.627
Campus da UFMG - Pampulha
CEP 31270-901
Belo Horizonte - Minas Gerais, Brasil

References

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H.M. Dalle, “Simulação do Reator Triga- IPR – R1 Utilizando Métodos de Transporte por Mon-te Carlo”. Tese de Doutorado, Universidade Estadual de Campinas, São Paulo. (2005).

Mesquita, A.Z.; Lage, A.M.F.; Martins, E.D.; Gual, M.R.; Palma, D.A.P. A human-machine in-terface for a Triga research reactor of Brazil. International Journal of Nuclear Energy, Science and Technology (Print), v. 10, p. 369-384, (2016). DOI: http://dx.doi.org/10.1504/IJNEST.2016.10002904.

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IAEA - International Atomic Energy Agency. Modernization of Instrumentation and Control in Nuclear Power Plants, IAEA-TECDOC-1016, IAEA, Vienna, 1998.

IAEA - International Atomic Energy Agency, “Specifications of Requirements for Upgrades Using Digital Instrumentation and Control Systems”, IAEA-TECDOC-1066, Vienna, 1999a.

IAEA - International Atomic Energy Agency, Modern Instrumentation and Control for Nuclear Power Plants: A Guidebook, Technical Reports Series No. 387, Vienna, 1999b.

IAEA - International Atomic Energy Agency. Specifications of Requirements for Upgrades Using Digital Instrumentation and Control Systems, IAEA-TECDOC-1066, Vienna, 1999c.

LAGE A. M. F, MESQUITA A. Z., and FELIPPE A. A. M. Design of a Digital System for Operational Parameters Simulation of IPRT-R1 Triga Nuclear Research Reactor, In: INTER-NATIONAL NUCLEAR ATLANTIC CONFERENCE, 2017, Belo Horizonte, 22-27 Oct 2017. p. 10-23.

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Published

2019-06-25

How to Cite

Lage, A. M. F., Felippe, A. A. M., & Mesquita, A. Z. (2019). Design of a digital system for operational parameters simulation of IPR-R1 Triga nuclear research reactor. Brazilian Journal of Radiation Sciences, 7(2B (Suppl.). https://doi.org/10.15392/bjrs.v7i2B.691

Issue

Section

XX Meeting on Nuclear Reactor Physics and Thermal Hydraulics (XX ENFIR)

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