Observatorio de I+D+i UPM

Memorias de investigación
Book chapters:
3D neutronic calculations: CAD-MCNP methodology applied to vessel activation in KOYO-F
Year:2008
Research Areas
  • Naval engineering
Information
Abstract
This paper presents a methodology for 3D neutronic calculations suitable for complex and extensive geometries. The geometry of the system design is first fully modelled with a CAD program, and subsequently processed through a MCNP-CAD interface in order to generate an MCNP geometry file. Neutronic irradiation results are finally achieved running the MCNPX program, where the geometry input card used is directly the MCNP-CAD interface output. This methodology enables accurate neutronic calculations for complex geometries characterised by high detail levels. This procedure will be applied to the Fast Ignition Fusion Reactor KOYO-F to determine first neutron fluxes calculations along the blanket as well as the material activation in the reduced martensitic 9Cr-1Mo steel vessel.
International
Si
10.1088/1742-6596/112/3/032046
Book Edition
0
Book Publishing
ISBN
1742-6596
Series
Book title
Journal of Physics: Conference Series
From page
1
To page
4
Participants
  • Autor: ANTONIO LAFUENTE
  • Autor: FERNANDO SORDO
  • Autor: Oscar Luis Cabellos De Francisco (UPM)
  • Autor: YURI HERRERAS
  • Autor: Jose Manuel Perlado Martin (UPM)
Research Group, Departaments and Institutes related
  • Creador: Grupo de Investigación: Fusión Nuclear Inercial y Tecnología de fusión
  • Departamento: Ingeniería Nuclear
  • Centro o Instituto I+D+i: Instituto de Fusión Nuclear
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