Isotopic prediction calculation methodologies: application to Vandellos-II Reactor cycles 7-11

Martínez, J.S. and Cabellos de Francisco, Oscar Luis and Diez de la Obra, Carlos Javier and Gilfillan, F. and Barbas, A. (2011). Isotopic prediction calculation methodologies: application to Vandellos-II Reactor cycles 7-11. In: "International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, MC 2011", 08/05/2011 - 12/05/2011, Río de Janeiro, Brasil.

Description

Title: Isotopic prediction calculation methodologies: application to Vandellos-II Reactor cycles 7-11
Author/s:
  • Martínez, J.S.
  • Cabellos de Francisco, Oscar Luis
  • Diez de la Obra, Carlos Javier
  • Gilfillan, F.
  • Barbas, A.
Item Type: Presentation at Congress or Conference (Article)
Event Title: International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, MC 2011
Event Dates: 08/05/2011 - 12/05/2011
Event Location: Río de Janeiro, Brasil
Title of Book: Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, MC 2011
Date: 2011
Subjects:
Freetext Keywords: Burnup credit, SCALE, MONTEBURNS, sensitivity/uncertainty, isotopic prediction
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

Determining as accurate as possible spent nuclear fuel isotopic content is gaining importance due to its safety and economic implications. Since nowadays higher burn ups are achievable through increasing initial enrichments, more efficient burn up strategies within the reactor cores and the extension of the irradiation periods, establishing and improving computation methodologies is mandatory in order to carry out reliable criticality and isotopic prediction calculations. Several codes (WIMSD5, SERPENT 1.1.7, SCALE 6.0, MONTEBURNS 2.0 and MCNP-ACAB) and methodologies are tested here and compared to consolidated benchmarks (OECD/NEA pin cell moderated with light water) with the purpose of validating them and reviewing the state of the isotopic prediction capabilities. These preliminary comparisons will suggest what can be generally expected of these codes when applied to real problems. In the present paper, SCALE 6.0 and MONTEBURNS 2.0 are used to model the same reported geometries, material compositions and burn up history of the Spanish Van de llós II reactor cycles 7-11 and to reproduce measured isotopies after irradiation and decay times. We analyze comparisons between measurements and each code results for several grades of geometrical modelization detail, using different libraries and cross-section treatment methodologies. The power and flux normalization method implemented in MONTEBURNS 2.0 is discussed and a new normalization strategy is developed to deal with the selected and similar problems, further options are included to reproduce temperature distributions of the materials within the fuel assemblies and it is introduced a new code to automate series of simulations and manage material information between them. In order to have a realistic confidence level in the prediction of spent fuel isotopic content, we have estimated uncertainties using our MCNP-ACAB system. This depletion code, which combines the neutron transport code MCNP and the inventory code ACAB, propagates the uncertainties in the nuclide inventory assessing the potential impact of uncertainties in the basic nuclear data: cross-section, decay data and fission yields

More information

Item ID: 11567
DC Identifier: http://oa.upm.es/11567/
OAI Identifier: oai:oa.upm.es:11567
Official URL: http://www.tandfonline.com/doi/abs/10.1080/00411450.2011.610205
Deposited by: Memoria Investigacion
Deposited on: 12 Dec 2012 17:46
Last Modified: 20 Apr 2016 19:36
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