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Título del libro: Ath 2020 - International Topical Meeting On Advances In Thermal Hydraulics
Título del capítulo: HEAT TRANSFER CORRELATIONS EFFECTS ON FUEL TEMPERATURE IN SCWR WITH FRACTIONAL NEUTRON POINT KINETICS

Autores UNAM:
JUAN LUIS FRANCOIS LACOUTURE; CECILIA MARTIN DEL CAMPO MARQUEZ; SERGIO QUEZADA GARCIA;

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Autores externos:

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Idioma:

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Año de publicación:
2020

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Palabras clave:

Activation energy; Heat transfer; Hydraulics; Kinetics; Mathematical operators; Neutrons; Correlation effect; Fractional neutron point kinetic; Fuel rods; Fuel temperature; Heat transfer correlation; Innovative design; Neutronics; SCWR; Thermal hydraulics; Time-space; Temperature

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Resumen:

The Super Critical Water Cooled Reactor is one of the most promising and innovative designs selected by the GIF. This is a very high-pressure water-cooled reactor which will operate at conditions above the thermodynamic critical point. In this work we present a numerical analysis of the effect of different heat transfer correlations on the prediction of the fuel temperature and wall cladding in a SCWR reactor which includes a Time-Space Fractional Neutron Point Kinetics (TSFNPK) model as a novelty, which considers a non-Fickian law for the neutron density current where the differential operators in space and time are of fractional order. The neutronic process with temperature feedback effects, the heat transfer in the fuel rod and the thermal hydraulics in the core were simulated. Fuel lattice neutronic calculations were performed with the HELIOS-2 code and the reactivity coefficients were used to evaluate the reactivity effects due to the fuel temperature and the supercritical water density for 177 energy groups. Due to the strong variation of coolant density through the core, five densities were considered. This safety parameter is calculated in order to evaluate the variation of the reactivity due to the Doppler Effect, as a function of the fuel temperature, which is related to the resonances broadening when the temperature increases. The coupling of neutronics (TSFNPK), heat transfer in the fuel rod, and thermal hydraulics is presented and numerical experiments due to changes in the mass flow rate were accomplished. © ATH 2020 - International Topical Meeting on Advances in Thermal Hydraulics.All rights reserved.

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Entidades citadas de la UNAM:

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Fuente:


ISBN:
9780894487774
Editorial:
American Nuclear Society

Tipo de producto:
Conference Paper