Memorias de investigación
Artículos en revistas:
Review of the C-nat(n,gamma) cross section and criticality calculations of the graphite moderated reactor BR1
Año:2013
Áreas de investigación
  • Ingenierías
Datos
Descripción
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.
Internacional
Si
JCR del ISI
Si
Título de la revista
ANNALS OF NUCLEAR ENERGY
ISSN
0306-4549
Factor de impacto JCR
0,905
Información de impacto
Volumen
60
DOI
10.1016/j.anucene.2013.05.003
Número de revista
Desde la página
210
Hasta la página
217
Mes
SIN MES
Ranking
0
Esta actividad pertenece a memorias de investigación
Participantes
  • Autor: Carlos Javier Diez De la Obra UPM
  • Autor: Oscar Luis Cabellos De Francisco UPM
  • Autor: a. stankovskiy
  • Autor: e. malambu
  • Autor: g. zerovnik
  • Autor: p. schillebeeckx
  • Autor: g. van den eynde
  • Autor: j. heyse
Grupos de investigación, Departamentos, Centros e Institutos de I+D+i relacionados
  • Creador: Grupo de Investigación: Fusión Nuclear Inercial y Tecnología de fusión
  • Centro o Instituto I+D+i: Instituto de Fusión Nuclear
  • Departamento: Ingeniería Nuclear