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

Herrero Carrascosa, José Javier and Ochoa Valero, Raquel and Martínez, J.S. and Díez, Carlos Javier and García Herranz, Nuria and Cabellos de Francisco, Oscar Luis (2013). Nuclear Data Uncertainty Propagation to Reactivity Coefficients of a Sodium Fast Reactor. In: "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.

Description

Title: Nuclear Data Uncertainty Propagation to Reactivity Coefficients of a Sodium Fast Reactor
Author/s:
  • Herrero Carrascosa, José Javier
  • Ochoa Valero, Raquel
  • Martínez, J.S.
  • Díez, Carlos Javier
  • García Herranz, Nuria
  • Cabellos de Francisco, Oscar Luis
Item Type: Presentation at Congress or Conference (Article)
Event Title: International Conference on Nuclear Data for Science and Technology
Event Dates: March 4-8, 2013
Event Location: New York, USA
Title of Book: Proceedings of the International Conference on Nuclear Data for Science and Technology - 2013
Date: 2013
Subjects:
Faculty: E.T.S.I. Industriales (UPM)
Department: Ingeniería Nuclear [hasta 2014]
Creative Commons Licenses: Recognition - No derivative works - Non commercial

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Abstract

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.

Funding Projects

TypeCodeAcronymLeaderTitle
FP7249671ANDES projectUnspecifiedUnspecified

More information

Item ID: 44366
DC Identifier: http://oa.upm.es/44366/
OAI Identifier: oai:oa.upm.es:44366
DOI: 10.1016/j.nds.2014.04.127
Official URL: http://www.sciencedirect.com/science/article/pii/S0090375214001574
Deposited by: Memoria Investigacion
Deposited on: 12 Jan 2017 12:00
Last Modified: 17 Jan 2017 08:51
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