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Assessment of a RELAP5 model for the IPR-R1 TRIGA research reactor
Authors:Patrí  cia A.L. Reis,Antonella L. Costa,Clá  ubia Pereira,Maria A.F. Veloso,Amir Z. Mesquita,Humberto V. Soares,Graiciany de P. Barros
Affiliation:1. Departamento de Engenharia Nuclear – Escola de Engenharia da Universidade Federal de Minas Gerais, Av. Antonio Carlos No. 6627, Campus Pampulha, PCA 1, CEP 31270-901, Belo Horizonte, MG, Brazil;2. Instituto Nacional de Ciências e Tecnologia de Reatores Nucleares Inovadores/CNPq, Brazil1;3. Centro de Desenvolvimento da Tecnologia Nuclear – CDTN/CNEN, Av. Antônio Carlos, 6627, Campus UFMG, Belo Horizonte, Brazil
Abstract:RELAP5 code was developed at the Idaho National Environmental and Engineering Laboratory and it is widely used for thermal hydraulic studies of commercial nuclear power plants and, currently, it has been also applied for thermal hydraulic analysis of nuclear research systems with good predictions. This work is a contribution to the assessment of RELAP5/3.3 code for research reactors analysis. It presents steady-state and transient calculation results performed using a RELAP5 model to simulate the IPR-R1 TRIGA research reactor conditions operating at 50 and 100 kW. The reactor is located at the Nuclear Technology Development Centre (CDTN), Brazil. The development and the assessment of a RELAP5 model for the IPR-R1 TRIGA are presented. Experimental data were considered in the process of code-to-data validation. The RELAP5 results were also compared with calculation performed using the STHIRP-1 (Research Reactors Thermal Hydraulic Simulation) code. The use of a cross flow model has been essential to improve results in the transient condition respect to preceding investigations.
Keywords:RELAP5   IPR-R1   TRIGA   Thermal hydraulic
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