Impact of nuclear data uncertainties on the reactivity of an astrid-like sodium fast reactor

Martínez Campo, Ana and García Herranz, Nuria and Romojaro, P. and Álvarez Velarde, F. and López, D. (2015). Impact of nuclear data uncertainties on the reactivity of an astrid-like sodium fast reactor. In: "41 Reunión anual de la Sociedad Nuclear Española", 23-25 septiembre 2015, A Coruña. pp. 1-8.

Description

Title: Impact of nuclear data uncertainties on the reactivity of an astrid-like sodium fast reactor
Author/s:
  • Martínez Campo, Ana
  • García Herranz, Nuria
  • Romojaro, P.
  • Álvarez Velarde, F.
  • López, D.
Item Type: Presentation at Congress or Conference (Article)
Event Title: 41 Reunión anual de la Sociedad Nuclear Española
Event Dates: 23-25 septiembre 2015
Event Location: A Coruña
Title of Book: Ponencias de la 41 Reunión Anual de la Sociedad Nuclear Española
Date: 2015
Subjects:
Faculty: E.T.S.I. Industriales (UPM)
Department: Ingeniería Energética
Creative Commons Licenses: Recognition - No derivative works - Non commercial

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Abstract

The EU 7th Framework Project ESNII+ was launched in 2013 in support of the initiative ESNII (European Sustainable Nuclear Industrial Initiative) whose purpose is to design, license, construct and begin the operation of the Sodium Fast Reactor Prototype, ASTRID, before 2025. An ASTRID-like core design has been analyzed (see other paper in this conference) and it was found to have a global negative reactivity feedback to sodium voiding. Taking into account the importance of feedback coefficients on core safety, the influence of the uncertainties in nuclear data should be assessed to have an exhaustive picture of the actual safety margins of ASTRID design. The objective of this work is to contribute to the improvement of the safety of ASTRID nuclear design by assessing different uncertainty propagation methodologies of the TSUNAMI-3D module of the SCALE system [1]. In this work, TSUNAMI-3D is applied to a pin-cell of the inner zone of the ASTRID core in order to select the optimal TSUNAMI-3D parameters. These parameters will be applied in future works to the Sensitivity and Uncertainty (S/U) analysis of the full core.

Funding Projects

TypeCodeAcronymLeaderTitle
FP7605172ESNII+ projectUnspecifiedEuropean Sustainable Nuclear Industrial Initiative

More information

Item ID: 41816
DC Identifier: http://oa.upm.es/41816/
OAI Identifier: oai:oa.upm.es:41816
Official URL: https://www.sne.es/es/agenda/actividades-organizadas-por-la-sne/reunion-anual
Deposited by: Memoria Investigacion
Deposited on: 14 Jul 2016 09:55
Last Modified: 14 Jul 2016 10:28
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