Experimental Estimation of Moderator Temperature Coefficient of the IPEN-MB-01 Reactor

Authors

  • Rubens Cavalcante da Silva University of São Paulo

DOI:

https://doi.org/10.15392/bjrs.v7i2B.615

Keywords:

IPEN/MB-01, Moderator Temperature Coefficient, Experimental Measurement

Abstract

The aim of this article is to present the procedure for the experimental estimation of the Moderator Temperature Coefficient of Reactivity of the IPEN/MB-01 Research Reactor, a parameter that has an important role in the physics and the control operations of any reactor facility. At the experiment, the IPEN/MB-01 reactor went critical at the power of 1W (1% of its total power), and whose core configuration was 28x26 rectangular array of UO2 fuel rods, inside a light water (moderator) tank. In addition, there was a heavy water (D2O) reflector installed in the West side of the core to obtain an adequate neutron reflection along the experiment. The moderator temperature was increased in steps of 4oC, and the measurement of the mean moderator temperature was acquired using twelve calibrated thermocouples, placed around the reactor core. As a result, the mean value of -4.81 pcm/°C was obtained for such coefficient. The curves of ρ(T) (Reactivity x Temperature) and  (Moderator Temperature Coefficient of Reactivity x Temperature) were developed using data from an experimental measurement of the integral reactivity curves through the Stable Period and Inverse Kinetics Methods, that was carried out at the reactor with the same core configuration. Such curves were compared and showed a very similar behavior between them.

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References

MOURTZANOS K.; HOUSIADAS C.; ANTONOPOULUS-DOMIS M. Calculation of the Moderator Temperature Coefficient of Reactivity for Water Moderated Reactors. In: Annals of Nuclear Energy, v. 28, p.1773-1782, 2001.

EDENIUS, M. Studies of the Reactivity Temperature Coefficient in Light Water Reactors. Chalmers University of Technology. Göteborg, 1976.

LEWIS, E. E. Fundamentals of Nuclear Reactor Physics. 1st ed. Academic Press, 2008.

NUCENG-Elementary Physics of Reactor Control. Available at: www.nuceng.ca/ep6p3/class/Module3C_Temp&VoidJun21.pdf (2016). Last Accessed: 15 Jan. 2017

CANTEACH-Science and Reactor Fundamentals – Reactor Physics. Available at: https://canteach.candu.org/Content%20Library/20030101.pdf (2010). Last Accessed: 23Jan. 2017.

BITELLI U. d’U ; MURA L. E. C.. IPN0025 - Física de Reatores: Experimentos no reator Nuclear IPEN/MB-01. Lectures Notes. Nuclear and Energy Research In-stitute. São Paulo, 2016.

HART S.W.D. Automated Doppler Broadening of Cross Sections for Neutron Transport Applications. PhD Thesis. University of Tennessee. Knoxville, 2014.

DUDERSTADT J.J; HAMILTON L. J. Nuclear Reactor Analysis. John Wiley & Sons. New York, 1976.

PINTO L. N. Experimentos de Efeitos de Reatividade no reator Nuclear IPEN/MB-01. Master Thesis. Nuclear and Energy Research Institute. São Paulo, 2012.

DA SILVA R. C; BITELLI U. d’U; MURA L.E.C. Experimento de Calibração das Barras de Controle do Reator IPEN/MB-01 pelo Método do Período Estável e da Cinética Inversa. Report of the IPN0025 Course – Reactor Physics: Experiments at IPEN/MB-01 Nuclear Reactor. Nuclear and Energy Research Institute. São Paulo, 2016.

IPEN – Nuclear and Energy Research Institute. Curso Preparatório de Operadores de Reator – Teoria Básica. v.1. São Paulo, 2000.

BITELLI U. d’U. Medida de Parâmetros Integrais no Reator IPEN/MB-01. Master Thesis, Nuclear and Energy Research Institute. São Paulo, 2001.

DOS SANTOS A. et al. Validation of neutronic models and calculation systems by means of experimental results in the IPEN/MB-01 reactor. In: Annals of Nuclear Energy, v. 60, p. 51-63, 2013.

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Published

2019-06-25

How to Cite

da Silva, R. C. (2019). Experimental Estimation of Moderator Temperature Coefficient of the IPEN-MB-01 Reactor. Brazilian Journal of Radiation Sciences, 7(2B (Suppl.). https://doi.org/10.15392/bjrs.v7i2B.615

Issue

Section

XX Meeting on Nuclear Reactor Physics and Thermal Hydraulics (XX ENFIR)