Experimental evaluation of natural convection in the IPR-R1 Triga research reactor at 264 kW and 105 kW

Authors

  • Amir Zacarias Mesquita Reactor Technology Department - Nuclear Technology Development Centre/Brazilian Nuclear Energy Commission (CDTN/Cnen)

DOI:

https://doi.org/10.15392/bjrs.v9i2B.1256

Keywords:

Triga Reactor, thermohydraulic, natural convection, temperature, radiation

Abstract

In order to study the safety aspects connected with the permanent increase of the maximum steady state power of the IPR-R1 Triga Reactor of the Nuclear Technology Development Center (CDTN), experimental measurements were done with the reactor operating at power levels of 265 kW and 105 kW, with the pool forced cooling system turned off. A number of parameters were measured in real-time such as fuel and water temperatures, radiation levels, reactivity, and influence of cooling system. Information on all aspects of reactor operation was displayed on the Data Acquisition System (DAS) shown the IPR-R1 online performance. The DAS was developed to monitor and record all operational parameters. Information displayed on the monitor was recorded on hard disk in a historical database. This paper summarizes the behavior of some operational parameters, and in particular, the evolution of the temperature in the fuel element centerline positioned in the core hottest location. The natural circulation test was performed to confirm the cooling capability of the natural convection in the IPR-R1 reactor. It was confirmed that the IPR-R1 has capability of long-term core cooling by natural circulation operating at 265 kW. The measured maximum fuel temperature of about 300 oC was lower than the operating limit of 550 oC. It has been proven that without cooling in the primary the gamma dose rate above reactor pool at high power levels was rather high.

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Author Biography

Amir Zacarias Mesquita, Reactor Technology Department - Nuclear Technology Development Centre/Brazilian Nuclear Energy Commission (CDTN/Cnen)

Bolsista de Produtividade em Pesquisa do CNPq .  Pesquisador de Produtividade e Desenvolvimento Tecnológico - DT/CNPq (2010-2016). Pesquisador Mineiro Fapemig (2008-2010) (2012-2015). Doutor em Engenharia Química - Universidade Estadual de Campinas/Unicamp (2005), mestre em Ciências Técnicas e Nucleares - Universidade Federal de Minas Gerais/UFMG (1981), graduado em Engenharia Elétrica - Universidade Federal de Minas Gerais/UFMG (1978). Pesquisador Titular III do Centro de Desenvolvimento da Tecnologia Nuclear/Comissão Nacional de Energia Nuclear (CDTN/Cnen). Docente Permanente (a partir de 2013) e Membro Titular do Colegiado (2014-2017) do Programa de Pós-Graduação em Ciência e Tecnologia das Radiações, Minerais e Materiais do CDTN.

References

MESQUITA, A.Z.; REZENDE, H.C.; PALMA, D.A.P. Performance of some operating parameters of a TRIGA research reactor in natural convective cooling. International Journal of Nuclear Energy, Science and Technology (Print), v. 8, p. 61-71. 2014. DOI: 10.1504/IJNEST.2014.057904.

MESQUITA, A.Z.; LAGE, A.M.F.; MARTINS, E. D.; GUAL, M. R.; PALMA, D.A.P. A human-machine interface for a Triga research reactor of Brazil. International Journal of Nuclear Energy, Science and Technology (Print), v. 10, p. 369-384. 2016. DOI: 10.1504/IJNEST.2016.082006.

MESQUITA, A.Z.; REZENDE, H.C.; SOUZA, R.M.G.P. Thermal Power Calibrations of the IPR-R1 TRIGA Reactor by the Calorimetric and the Heat Balance Methods. Progress in Nuclear Energy (New Series), v. 53, p. 1197-1203. 2011. DOI: 10.1016/j.pnucene.2011.08.003.

GULF GENERAL ATOMIC. 15” SST fuel element assembly instrumented core. San Diego, CA. Drawing Number TOS210J220. 1972.

MESQUITA, A.Z. Termo-Hidráulica Experimental de Reator Nuclear de Pesquisa Triga. 1. ed. Saarbrücken - Alemanha: Novas Edições Acadêmicas - OmniScriptum GmbH & Co. KG, v. 1. 2015.

SIMNAD, M. T. The U-ZrHx alloys: its properties and use in TRIGA fuel. Nuclear Engineering and Design, v. 64:403-422. 1981.

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Published

2021-07-25

How to Cite

Mesquita, A. Z. (2021). Experimental evaluation of natural convection in the IPR-R1 Triga research reactor at 264 kW and 105 kW. Brazilian Journal of Radiation Sciences, 9(2B (Suppl.). https://doi.org/10.15392/bjrs.v9i2B.1256

Issue

Section

XXI Meeting on Nuclear Reactor Physics and Thermal Hydraulics (XXI ENFIR) and VI ENIN

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