Review and comparison of effective delayed neutron fraction calculation methods with Monte Carlo codes

Bécares, V.; Pérez Martín, S.; Vázquez Antolín, Miriam; Villamarín, D.; Martín Fuertes, Francisco; González Romero, E.M. y Merino Rodríguez, Iván (2014). Review and comparison of effective delayed neutron fraction calculation methods with Monte Carlo codes. "Annals of Nuclear Energy", v. 65 (n. null); pp. 402-410. ISSN 0306-4549. https://doi.org/10.1016/j.anucene.2013.11.038.

Descripción

Título: Review and comparison of effective delayed neutron fraction calculation methods with Monte Carlo codes
Autor/es:
  • Bécares, V.
  • Pérez Martín, S.
  • Vázquez Antolín, Miriam
  • Villamarín, D.
  • Martín Fuertes, Francisco
  • González Romero, E.M.
  • Merino Rodríguez, Iván
Tipo de Documento: Artículo
Título de Revista/Publicación: Annals of Nuclear Energy
Fecha: 2014
Volumen: 65
Materias:
Palabras Clave Informales: Effective delayed neutron fraction, Adjoint flux, Monte Carlo, MCNPX
Escuela: E.T.S.I. Industriales (UPM)
Departamento: Otro
Licencias Creative Commons: Reconocimiento - Sin obra derivada - No comercial

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Resumen

The calculation of the effective delayed neutron fraction, beff , with Monte Carlo codes is a complex task due to the requirement of properly considering the adjoint weighting of delayed neutrons. Nevertheless, several techniques have been proposed to circumvent this difficulty and obtain accurate Monte Carlo results for beff without the need of explicitly determining the adjoint flux. In this paper, we make a review of some of these techniques; namely we have analyzed two variants of what we call the k-eigenvalue technique and other techniques based on different interpretations of the physical meaning of the adjoint weighting. To test the validity of all these techniques we have implemented them with the MCNPX code and we have benchmarked them against a range of critical and subcritical systems for which either experimental or deterministic values of beff are available. Furthermore, several nuclear data libraries have been used in order to assess the impact of the uncertainty in nuclear data in the calculated value of beff .

Proyectos asociados

TipoCódigoAcrónimoResponsableTítulo
FP7232527 / 232658 / 269665CDT– Central Design Team for a Fast Spectrum Transmutation Experimental Facility, CP-ESF, FREYA (Fast Reactor Experiments for hYbrid Applications),Sin especificarCDT– Central Design Team for a Fast Spectrum Transmutation Experimental Facility, CP-ESF, FREYA (Fast Reactor Experiments for hYbrid Applications),

Más información

ID de Registro: 33093
Identificador DC: http://oa.upm.es/33093/
Identificador OAI: oai:oa.upm.es:33093
Identificador DOI: 10.1016/j.anucene.2013.11.038
URL Oficial: http://www.sciencedirect.com/science/article/pii/S030645491300635X
Depositado por: Memoria Investigacion
Depositado el: 12 Dic 2014 16:48
Ultima Modificación: 19 Dic 2014 17:26
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