Observatorio de I+D+i UPM

Memorias de investigación
Ponencias en congresos:
Evaluation of permeable and non-permeable tritium in normal condition in a fusion reactor
Año:2007
Áreas de investigación
  • Ingeniería naval
Datos
Descripción
The tritium cycle is centered in the Internal Regenerator Cycle. The tritium could be recovered from a flow of He gas, or directly from solid breeder. The limits of transfers to the atmosphere are assumed ~ 1 gr-T/a (~20 Ci/a) (without species distinction). The transfer limits determine the key parameters in tritium Cycle (HT, HTO, as dominant, and T2, T2O as marginal). Presently, the transfer from the cycle to the environment is assumed through the exchange system of the power plant (primary to secondary). That transport is due to the permeation through HT, T2, or leakage to the coolant in the primary system. It is key the chemical optimitation in the primary system, that needs to be reanalyzed in terms of radiological impact both for permeable, HT, T2, and non-permeable HTO, T2O. It is necessary considered the pathway of tritium from the reactor to the atmosphere, these processes are modelled adequately. Results of the assessments were early and chronic doses which have been evaluated for the Most Exposed Individual at particular distance bands from the release point.
Internacional
Si
Nombre congreso
Fifth International Conference on Inertial Fusion Sciences and Applications (IFSA-07)
Tipo de participación
960
Lugar del congreso
Kobe (Japón)
Revisores
No
ISBN o ISSN
DOI
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Fecha fin congreso
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Título de las actas
Esta actividad pertenece a memorias de investigación
Participantes
  • Participante: LUIS SEDANO
  • Autor: Jose Manuel Perlado Martin (UPM)
  • Autor: Marta Velarde Mayol (UPM)
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
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