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Título del libro: Pbnc 2018 - Pacific Basin Nuclear Conference
Título del capítulo: Neutronic study of the nuscale core with different fuel types

Autores UNAM:
JUAN LUIS FRANCOIS LACOUTURE;
Autores externos:

Idioma:
Inglés
Año de publicación:
2019
Palabras clave:

Nuclear fuels; Uranium dioxide; Zirconium compounds; Advanced fuels; Integral designs; Monte Carlo codes; Neutronic studies; Operating cycle; Passive systems; Small modular reactors; Temperature coefficient; Silicon compounds


Resumen:

Safety is a concept that has recently drawn attention in the Small Modular Reactors, among which the NuScale, in particular, stands out. This reactor offers a unique integral design with enrichment below 5%, a thermal power of 160 MW and 24-month operating cycles, also guaranteeing safe shutdown by redundant passive systems. In this work the core of the NuScale reactor is simulated with the Serpent Monte Carlo code, with the objective of analyzing important steady state core parameters and making a comparison between different advanced fuels, such as ceramic fuels (UO2, U3Si2) and metallic fuels (U-10Zr). The results predict the behavior of the core through Keff and ppm of boron vs fuel burnup, as well as the Doppler coefficient and moderator density and temperature coefficients. © 2018 PBNC 2018 - Pacific Basin Nuclear Conference.All Rights Reserved.


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