Thermal hydraulic analysis of the IPR-R1 TRIGA research reactor using a RELAP5 model |
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Authors: | Antonella L. Costa,Patrí cia Amé lia L. Reis,Clá ubia Pereira,Maria Auxiliadora F. Veloso,Amir Z. Mesquita |
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Affiliation: | a Departamento de Engenharia Nuclear - Escola de Engenharia da Universidade Federal de Minas Gerais, Av. Antonio Carlos, n° 6627, Campus UFMG, PCA 1, CEP 31270-901, Belo Horizonte, MG, Brazil b Instituto Nacional de Ciências e Tecnologia de Reatores Nucleares Inovadores/CNPq, Brazil1 c Centro de Desenvolvimento da Tecnologia Nuclear - CDTN/CNEN, Av. Antônio Carlos, 6627, Campus UFMG, Belo Horizonte, Brazil |
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Abstract: | The RELAP5 code is widely used for thermal hydraulic studies of commercial nuclear power plants. Current investigations and code adaptations have demonstrated that the RELAP5 code can be also applied for thermal hydraulic analysis of nuclear research reactors with good predictions. Therefore, as a contribution to the assessment of RELAP5/MOD3.3 for research reactors analysis, this work presents steady-state and transient calculation results performed using a RELAP5 model to simulate the IPR-R1 TRIGA research reactor at 50 kilowatts (kW) of power operation. The reactor is located in the Nuclear Technology Development Center (CDTN), Brazil. It is a 250 kW, light water moderated and cooled, graphite-reflected, open pool type research reactor. The development and the assessment of a RELAP5 model for the IPR-R1 TRIGA are presented. Experimental data were considered in the process of the RELAP5 model validation. The RELAP5 results were also compared with calculated data from the STHIRP-1 (Research Reactors Thermal Hydraulic Simulation) code. The results obtained have shown that the RELAP5 model for the IPR-R1 TRIGA reproduces the actual steady-state reactor behavior in good agreement with the available data. |
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