Nuclear Data Uncertainty Propagation to Reactivity Coefficients of a Sodium Fast Reactor

Herrero Carrascosa, José Javier; Ochoa Valero, Raquel; Martínez, J.S.; Díez, Carlos Javier; García Herranz, Nuria y Cabellos de Francisco, Oscar Luis (2013). Nuclear Data Uncertainty Propagation to Reactivity Coefficients of a Sodium Fast Reactor. En: "International Conference on Nuclear Data for Science and Technology", March 4-8, 2013, New York, USA. pp. 1-3. https://doi.org/10.1016/j.nds.2014.04.127.

Descripción

Título: Nuclear Data Uncertainty Propagation to Reactivity Coefficients of a Sodium Fast Reactor
Autor/es:
  • Herrero Carrascosa, José Javier
  • Ochoa Valero, Raquel
  • Martínez, J.S.
  • Díez, Carlos Javier
  • García Herranz, Nuria
  • Cabellos de Francisco, Oscar Luis
Tipo de Documento: Ponencia en Congreso o Jornada (Artículo)
Título del Evento: International Conference on Nuclear Data for Science and Technology
Fechas del Evento: March 4-8, 2013
Lugar del Evento: New York, USA
Título del Libro: Proceedings of the International Conference on Nuclear Data for Science and Technology - 2013
Fecha: 2013
Materias:
Escuela: E.T.S.I. Industriales (UPM)
Departamento: Ingeniería Nuclear [hasta 2014]
Licencias Creative Commons: Reconocimiento - Sin obra derivada - No comercial

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Resumen

Engineering of innovative reactor concepts requires computational tools capable of producing results with a high level of accuracy. These results are affected by different sources of uncertainty such as the ones coming from nuclear data. The assessment of the uncertainty levels on the design and safety parameters is mandatory. The uncertainty quantification applied here is based on the adjoint sensitivity analysis, where the sensitivities of design values to nuclear data are employed together with the nuclear data uncertainties to propagate these uncertainties to the design parameters. The European Sodium Fast Reactor (ESFR) is the innovative reactor model considered here, designed in the framework of a EURATOM Collaborative Project. Some of the relevant safety quantities linked to it are Doppler and void reactivity coefficients, whose uncertainties are quantified. Also the identification of the nuclear reaction data where an improvement will certainly benefit the design accuracy is performed. This work has been performed with the SCALE 6.1 codes suite and its multigroups cross sections library based on ENDF/B-VII.0 evaluation.

Proyectos asociados

TipoCódigoAcrónimoResponsableTítulo
FP7249671ANDES projectSin especificarSin especificar

Más información

ID de Registro: 44366
Identificador DC: http://oa.upm.es/44366/
Identificador OAI: oai:oa.upm.es:44366
Identificador DOI [BETA]: 10.1016/j.nds.2014.04.127
URL Oficial: http://www.sciencedirect.com/science/article/pii/S0090375214001574
Depositado por: Memoria Investigacion
Depositado el: 12 Ene 2017 12:00
Ultima Modificación: 17 Ene 2017 08:51
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