Experimental evaluation of natural convection in the IPR-R1 Triga research reactor at 264 kW and 105 kW
DOI:
https://doi.org/10.15392/bjrs.v9i2B.1256Palabras clave:
Triga Reactor, thermohydraulic, natural convection, temperature, radiationResumen
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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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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Derechos de autor 2021 Brazilian Journal of Radiation Sciences (BJRS)
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