Nuclear data sensitivity and uncertainty analysis of effective neutron multiplication factor in various MYRRHA core configurations

Romojaro Otero, Pablo; Álvarez-Velarde, Francisco; Kodeli, I.; Stankovskiy, Alexey; Díez, C. J.; Cabellos, O.; García Herranz, Nuria; Heyse, Jan; Schillebeeckx, Peter; Van den Eynde, Gert y Zerovnik, Gasper (2017). Nuclear data sensitivity and uncertainty analysis of effective neutron multiplication factor in various MYRRHA core configurations. "Annals of Nuclear Energy", v. 101 ; pp. 330-338. ISSN 0306-4549. https://doi.org/10.1016/j.anucene.2016.11.027.

Descripción

Título: Nuclear data sensitivity and uncertainty analysis of effective neutron multiplication factor in various MYRRHA core configurations
Autor/es:
  • Romojaro Otero, Pablo
  • Álvarez-Velarde, Francisco
  • Kodeli, I.
  • Stankovskiy, Alexey
  • Díez, C. J.
  • Cabellos, O.
  • García Herranz, Nuria
  • Heyse, Jan
  • Schillebeeckx, Peter
  • Van den Eynde, Gert
  • Zerovnik, Gasper
Tipo de Documento: Artículo
Título de Revista/Publicación: Annals of Nuclear Energy
Fecha: Marzo 2017
Volumen: 101
Materias:
Palabras Clave Informales: MYRRHA, Nuclear data, Sensitivity and uncertainty, Covariance, Lead-bismuth cooled fast reactor, ADS
Escuela: E.T.S.I. Industriales (UPM)
Departamento: Ingeniería Energética
Licencias Creative Commons: Reconocimiento - Sin obra derivada - No comercial

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Resumen

A sensitivity and uncertainty analysis was carried out to estimate the uncertainty in the neutron multiplication factor keff and to identify the most important nuclear data for neutron induced reactions for criticality calculations of the latest MYRRHA designs. Sensitivity profiles, i.e. sensitivity to the nuclear data as a function of incoming neutron energy, were derived for both a critical and sub-critical core. They were calculated using codes that are based on different methodologies including stochastic and deterministic calculations (i.e. SCALE, MCNP and XSUN). The neutron induced nuclear data sensitivity analysis outlined the following quantities to be of special importance for the MYRRHA reactor concept: 239Pu(n,c) both in resonance and fast energy region, (n,f) fast, v and m fast; 238U(n,n0 ) fast, (n,c) resonance and fast, (n,n) resonance and fast; 240Pu m fast; 238Pu(n,f) both resonance and fast; 56Fe(n,c) both resonance and fast. Differences of less than 4% between codes were obtained for these quantities, with few exceptions ( 238Pu(n,f), 238U(n,n) and 56Fe(n,c) reactions). Nuclear data covariance matrices of different libraries (SCALE-6, COMMARA-2 and JENDL-4.0m) were used to derive the uncertainty in keff based on the calculated sensitivities. This study reveals that the largest contributions to keff uncertainty result from the uncertainty in the average prompt neutron fission multiplicity of 239Pu, in the 238U inelastic scattering cross section and 239Pu fission cross section, using the covariances from SCALE-6, COMMARA-2 and JENDL-4.0m, respectively.

Proyectos asociados

TipoCódigoAcrónimoResponsableTítulo
FP7605203Sin especificarSin especificarCHANDA project

Más información

ID de Registro: 49886
Identificador DC: http://oa.upm.es/49886/
Identificador OAI: oai:oa.upm.es:49886
Identificador DOI: 10.1016/j.anucene.2016.11.027
URL Oficial: https://www.sciencedirect.com/science/article/pii/S030645491630500X?via%3Dihub
Depositado por: Memoria Investigacion
Depositado el: 17 May 2018 15:16
Ultima Modificación: 17 May 2018 15:16
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