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Hindi Research Article, J Nucl Ene Sci Power Generat Technol Vol: 6 Issue: 2
Thermal Hydraulic Analysis and Modeling of the HTTR Using the RELAP5-3D
| Scari ME1,2, Costa AL1,2*, Ramos MC1,2 and Pereira C1,2 | |
| 1Departamento de Engenharia Nuclear, Universidade Federal de Minas Gerais, Brazil | |
| 2Instituto Nacional de Ciências e Tecnologia de Reatores Nucleares Inovadores/ CNPq, Brazil | |
| Corresponding author : Antonella L. Costa
Department of Nuclear Engineering, Federal University of Minas Gerais, Brazil Tel: +553134096688 E-mail: antonella@nuclear.ufmg.br |
|
| Received: January 24, 2017 Accepted: February 08, 2017 Published: February 27, 2017 | |
| Citation: Scari ME, Costa AL, Ramos MC, Pereira C (2017) Thermal Hydraulic Analysis and Modeling of the HTTR Using the RELAP5-3D. J Nucl Ene Sci Power Generat Technol 6:2. doi: 10.4172/2325-9809.1000174 |
Abstract
A thermal hydraulic model for the HTTR (High Temperature Engineering Test Reactor) has been developed using the RELAP5-3D code. The HTTR is a high temperature gas-cooled reactor (HTGR) developed, designed, constructed, and operated by the Japan Atomic Energy Research Institute (JAERI). It is a helium-cooled and graphite-moderated with a thermal power of 30 MW. In this work, a HTTR core inlet and outlet coolant temperatures, mass flow rate, pressure drop and heat structures (fuel and graphite block) temperatures have been reproduced using a RELAP5 model. The simulation was done in the high temperature operation mode (950°C) and in the rated operation mode (850 °C). The results have been compared with the available data. The calculations were performed using the point kinetic model. It is demonstrated that the developed model in the RELAP5-3D is capable of reproduce the thermal behavior of the reactor in steady state operation.
