Observatorio de I+D+i UPM

Memorias de investigación
Communications at congresses:
Evaluation of permeable and non-permeable tritium in normal condition in a fusion reactor
Year:2007
Research Areas
  • Naval engineering
Information
Abstract
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.
International
Si
Congress
Fifth International Conference on Inertial Fusion Sciences and Applications (IFSA-07)
960
Place
Kobe (Japón)
Reviewers
No
ISBN/ISSN
Start Date
End Date
From page
To page
Participants
  • Participante: LUIS SEDANO
  • Autor: Jose Manuel Perlado Martin (UPM)
  • Autor: Marta Velarde Mayol (UPM)
Research Group, Departaments and Institutes related
  • 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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