Memorias de investigación
Communications at congresses:
Effect of ion flux on helium retention in helium-irradiated tungsten (POSTER)
Year:2012
Research Areas
  • Engineering
Information
Abstract
Tungsten is considered an appropriate material for nuclear fusion reactors However, there exist serious concerns on W survivability under severe irradiation conditions ?Irradiation-induced defects may be detrimental even in samples with good thermo-mechanical response ?He retention in irradiated tungsten ? swelling, pore formation, sample exfoliation, mass loss ?Both in magnetic and in inertial fusion the most detrimental situations take place with high flux pulses ?Pore formation thresholds depend on He flux, Refs. [1,2] ?This could be due to He retention [1] but these effects are not well understood due to the subtleties imposed by the exact temperature profile, ion energy, pulse duration and the presence of impurities ?Object Kinetic Monte Carlo (OKMC) is the technique of choice to simulate the evolution of radiation-induced damage inside solids in large temporal and space scales. ?We have used the recently developed code MMonCa (Modular Monte Carlo simulator), presented in this conference for the first time, to study He retention in W samples
International
Si
Congress
Computer Simulation of Radiation Effects in Solids (COSIRES 2012)
960
Place
Santa Fe, USA
Reviewers
Si
ISBN/ISSN
0000-0000
Start Date
24/06/2012
End Date
29/06/2012
From page
1
To page
1
Proceedings
Participants
  • Autor: Antonio Juan Rivera de Mena UPM
  • Autor: G. Valles Instituto de Fusión Nuclear
  • Autor: M.J. Caturla Universidad de Alicante
  • Autor: I. Martín-Bragado
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