Review of the C-nat(n,gamma) cross section and criticality calculations of the graphite moderated reactor BR1

Diez de la Obra, Carlos Javier; Stankovskiy, Alexey; Malambu, E.; Zerovnik, Gasper; Schillebeeckx, Peter; Van den Eynde, Gert; Heyse, Jan y Cabellos de Francisco, Oscar Luis (2013). Review of the C-nat(n,gamma) cross section and criticality calculations of the graphite moderated reactor BR1. "Annals of Nuclear Energy", v. 60 ; pp. 210-217. ISSN 0306-4549. https://doi.org/10.1016/j.anucene.2013.05.003.

Descripción

Título: Review of the C-nat(n,gamma) cross section and criticality calculations of the graphite moderated reactor BR1
Autor/es:
  • Diez de la Obra, Carlos Javier
  • Stankovskiy, Alexey
  • Malambu, E.
  • Zerovnik, Gasper
  • Schillebeeckx, Peter
  • Van den Eynde, Gert
  • Heyse, Jan
  • Cabellos de Francisco, Oscar Luis
Tipo de Documento: Artículo
Título de Revista/Publicación: Annals of Nuclear Energy
Fecha: Octubre 2013
Volumen: 60
Materias:
Palabras Clave Informales: Thermal capture; Cross section; Graphite reactor; Carbon; Criticality; Nuclear data
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

A review of the experimental data for natC(n,c) and 12C(n,c) was made to identify the origin of the natC capture cross sections included in evaluated data libraries and to clarify differences observed in neutronic calculations for graphite moderated reactors using different libraries. The performance of the JEFF-3.1.2 and ENDF/B-VII.1 libraries was verified by comparing results of criticality calculations with experimental results obtained for the BR1 reactor. This reactor is an air-cooled reactor with graphite as moderator and is located at the Belgian Nuclear Research Centre SCK-CEN in Mol (Belgium). The results of this study confirm conclusions drawn from neutronic calculations of the High Temperature Engineering Test Reactor (HTTR) in Japan. Furthermore, both BR1 and HTTR calculations support the capture cross section of 12C at thermal energy which is recommended by Firestone and Révay. Additional criticality calculations were carried out in order to illustrate that the natC thermal capture cross section is important for systems with a large amount of graphite. The present study shows that only the evaluation carried out for JENDL-4.0 reflects the current status of the experimental data.

Más información

ID de Registro: 25690
Identificador DC: http://oa.upm.es/25690/
Identificador OAI: oai:oa.upm.es:25690
Identificador DOI: 10.1016/j.anucene.2013.05.003
URL Oficial: http://www.sciencedirect.com/science/article/pii/S030645491300251X
Depositado por: Memoria Investigacion
Depositado el: 05 May 2014 17:18
Ultima Modificación: 01 Nov 2015 23:56
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