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

Bécares, V. and Pérez Martín, S. and Vázquez Antolín, Miriam and Villamarín, D. and Martín Fuertes, Francisco and González Romero, E.M. and 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.

Description

Title: Review and comparison of effective delayed neutron fraction calculation methods with Monte Carlo codes
Author/s:
  • Bécares, V.
  • Pérez Martín, S.
  • Vázquez Antolín, Miriam
  • Villamarín, D.
  • Martín Fuertes, Francisco
  • González Romero, E.M.
  • Merino Rodríguez, Iván
Item Type: Article
Título de Revista/Publicación: Annals of Nuclear Energy
Date: 2014
ISSN: 0306-4549
Volume: 65
Subjects:
Freetext Keywords: Effective delayed neutron fraction, Adjoint flux, Monte Carlo, MCNPX
Faculty: E.T.S.I. Industriales (UPM)
Department: Otro
Creative Commons Licenses: Recognition - No derivative works - Non commercial

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Abstract

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 .

Funding Projects

TypeCodeAcronymLeaderTitle
FP7232527CDTSTUDIECENTRUM VOOR KERNENERGIE / CENTRE D'ETUDE DE L'ENERGIE NUCLEAIRECentral Design Team (CDT) for a Fast-spectrum Transmutation Experimental Facility
FP7232658CP-ESFRCOMMISSARIAT A L ENERGIE ATOMIQUE ET AUX ENERGIES ALTERNATIVESCollaborative Project on European Sodium Fast Reactor
FP7269665FREYASTUDIECENTRUM VOOR KERNENERGIE / CENTRE D'ETUDE DE L'ENERGIE NUCLEAIREFast Reactor Experiments for hYbrid Applications

More information

Item ID: 33093
DC Identifier: http://oa.upm.es/33093/
OAI Identifier: oai:oa.upm.es:33093
DOI: 10.1016/j.anucene.2013.11.038
Official URL: http://www.sciencedirect.com/science/article/pii/S030645491300635X
Deposited by: Memoria Investigacion
Deposited on: 12 Dec 2014 16:48
Last Modified: 14 May 2019 12:34
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