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

Martínez, J.S.; Cabellos de Francisco, Oscar Luis; Diez de la Obra, Carlos Javier; Gilfillan, F. y Barbas, A. (2011). Isotopic prediction calculation methodologies: application to Vandellos-II Reactor cycles 7-11. En: "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.

Descripción

Título: Isotopic prediction calculation methodologies: application to Vandellos-II Reactor cycles 7-11
Autor/es:
  • Martínez, J.S.
  • Cabellos de Francisco, Oscar Luis
  • Diez de la Obra, Carlos Javier
  • Gilfillan, F.
  • Barbas, A.
Tipo de Documento: Ponencia en Congreso o Jornada (Artículo)
Título del Evento: International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, MC 2011
Fechas del Evento: 08/05/2011 - 12/05/2011
Lugar del Evento: Río de Janeiro, Brasil
Título del Libro: Proceedings of the International Conference on Mathematics and Computational Methods Applied to Nuclear Science and Engineering, MC 2011
Fecha: 2011
Materias:
Palabras Clave Informales: Burnup credit, SCALE, MONTEBURNS, sensitivity/uncertainty, isotopic prediction
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

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

Más información

ID de Registro: 11567
Identificador DC: http://oa.upm.es/11567/
Identificador OAI: oai:oa.upm.es:11567
URL Oficial: http://www.tandfonline.com/doi/abs/10.1080/00411450.2011.610205
Depositado por: Memoria Investigacion
Depositado el: 12 Dic 2012 17:46
Ultima Modificación: 20 Abr 2016 19:36
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