Power calibration of the TRIGA mark I nuclear research reactor

AUTOR(ES)

Mesquita, Amir Z., Rezende, Hugo Cesar, Tambourgi, Elias B.

FONTE

Journal of the Brazilian Society of Mechanical Sciences and Engineering

DATA DE PUBLICAÇÃO

2007-09

RESUMO

This paper presents the results and methodology used to calibrate the thermal power of the TRIGA Mark I IPR-R1 Research Reactor at the Nuclear Technology Development Centre (CDTN), in Belo Horizonte, Brazil. The TRIGA Mark I is a pool type reactor, cooled by water natural convection. The method used in the calibration consisted in the steady-state energy balance of the primary cooling loop of the reactor. For this balance, the inlet and outlet temperatures and the water flow in this primary cooling loop were measured. The heat transferred through the primary loop was added to the heat leakage from the reactor pool. The thermal losses from the primary loop were not evaluated since the inlet and outlet temperatures were measured just above the water surface of the reactor pool. The temperature of the water in the reactor pool as well as the reactor room temperature were set as close as possible to the soil temperature to minimize heat leakages. These leakages are mainly due to the conduction through the concrete and metal walls and also due to the evaporation and convection through the water surface of the reactor pool.

Documentos Relacionados

• Levantamento de parametros nucleares do reator TRIGA MARK I IPR RI com configuração concentrica visando a aplicação da tecnica de ativação neutronica Ko
• DIGITAL SIMULATION SYSTEM OF NEUTRON PARAMETERS OF THE TRIGA IPR-R1 NUCLEAR RESEARCH REACTOR
• Thermal and epithermal neutron fluence rates in the irradiation facilities of the TRIGA IPR-R1 nuclear reactor
• Multivariable robust control of an integrated nuclear power reactor
• Specific induced activity profile at the rotary specimen rack of IPR-R1 TRIGA reactor