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Título del libro: International Conference On Physics Of Reactors, Physor 2018: Reactor Physics Paving The Way Towards More Efficient Systems
Título del capítulo: Neutronic study of the astrid sodium-cooled fast reactor with thorium based fuel

Autores UNAM:
JUAN LUIS FRANCOIS LACOUTURE;

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Autores externos:

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Idioma:

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Año de publicación:
2018

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Palabras clave:

Coolants; Fuels; Pavements; Thorium; Coolant density; Cross-section library; Doppler constant; ENDF/B-VII.0; Neutron multiplication; Neutronic studies; Temperature raise; Thorium based fuels; Sodium-cooled fast reactors

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Resumen:

In the present work the utilization of thorium is investigated in the sodium-cooled ASTRID fast reactor core. Two thorium fueled strategies are analyzed: a mixture of 232Th and 233U in the fertile zone, and both in the fertile and the fissile zone core. To achieve this, the Monte Carlo MCNP6 code with the ENDF/B-VII.0 cross section library was used to perform the calculations. Three neutronic parameters were analyzed for each fuel strategy: the effective neutron multiplication factor (keff) for a cycle of 360 days, the Doppler constant and the reactivity effect of coolant density. Main isotopes evolution was also analyzed. The keff in the reference core and with thorium in the fertile zone is very similar, getting the second one higher keff at the EoC The keff with thorium in the whole core has a significant loss in reactivity and need further research. As in the reference core, 239Pu is bred, the same happens with 233U in the core with thorium in the fertile zone. This does not happen with thorium in the whole core. The Am and Cm actinides concentrations are lower with thorium in the fertile zone than in the reference core, and are completely absent with thorium in the whole core. For all the fuel configurations, the Doppler constant and the reactivity effect of coolant density are good, as the keff drops with temperature raise or with void raise. In the case of voiding we have a better performance with thorium in the whole core. Copyright © (2018) by PHYSOR 2018.

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Entidades citadas de la UNAM:

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Fuente:


ISBN:
9781713808510
Editorial:
Sociedad Nuclear Mexicana, A.C.

Tipo de producto:
Conference Paper