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

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Veröffentlicht: Sociedade Brasileira de Proteção Radiológica - SBPR 2021
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author A.Z. Mesquita
author_facet A.Z. Mesquita
contents Experimental evaluation of natural convection in the IPR-R1 Triga research reactor at 264 kW and 105 KW A.Z. Mesquita H.C Rezende R.R Rodrigues V. F Almeida D.A.P Palma Biología radiation temperature Triga Reactor thermohydraulic natural convection 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. 2021 artículo científico 2319-0612 https://www.redalyc.org/articulo.oa?id=722280949002 en http://www.redalyc.org/revista.oa?id=7222 Brazilian Journal of Radiation Sciences application/pdf Sociedade Brasileira de Proteção Radiológica - SBPR Brazilian Journal of Radiation Sciences (Brasil) Num.2B Vol.9
format Artículo científico
id redalyc_722280949002
institution Redalyc
language en
publishDate 2021
publisher Sociedade Brasileira de Proteção Radiológica - SBPR
spellingShingle Experimental evaluation of natural convection in the IPR-R1 Triga research reactor at 264 kW and 105 KW
A.Z. Mesquita
Biología
radiation
temperature
Triga Reactor
thermohydraulic
natural convection
Experimental evaluation of natural convection in the IPR-R1 Triga research reactor at 264 kW and 105 KW A.Z. Mesquita H.C Rezende R.R Rodrigues V. F Almeida D.A.P Palma Biología radiation temperature Triga Reactor thermohydraulic natural convection 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. 2021 artículo científico 2319-0612 https://www.redalyc.org/articulo.oa?id=722280949002 en http://www.redalyc.org/revista.oa?id=7222 Brazilian Journal of Radiation Sciences application/pdf Sociedade Brasileira de Proteção Radiológica - SBPR Brazilian Journal of Radiation Sciences (Brasil) Num.2B Vol.9
title Experimental evaluation of natural convection in the IPR-R1 Triga research reactor at 264 kW and 105 KW
topic Biología
radiation
temperature
Triga Reactor
thermohydraulic
natural convection
url https://www.redalyc.org/articulo.oa?id=722280949002