Tritium permeation issues for helium-cooled breeding blankets

F. Franza, L.V. Boccaccini, D. Demange, A. Ciampichetti, M. Zucchetti

Research output: Contribution to conferencePaper

Abstract

Tritium permeation through Breeding Blanket and Steam Generator heat transfer areas is a crucial aspect for the design of the next generation DEMO fusion power plants. Tritium is generated inside the breeder, dissolves in and permeates through materials, thus leading to a potential hazard for the environment. For this reason it is important to carry out the tritium migration analysis for a specific DEMO blanket configuration in order to predict the released amount of tritium during the plant operation. Unfortunately, tritium assessments are often affected by several uncertainties implying very important modelling and parametric issues. In this study the main permeation issues are identified and possible solutions are discussed to face the modelling issues and the parametric uncertainties affecting the T migration assessments for the two DEMO helium-cooled breeding blankets, i.e.: 1) Helium-Cooled Pebble Beds (HCPB) and 2) Helium-Cooled Lithium-Lead (HCLL). For these two helium-cooled blanket concepts various tritium migration analyses will be carried out by means of the computational tool FUS-TPC in order to define proper and feasible tritium mitigation techniques which are needed to keep the tritium losses lower than the allowable environmental release (i.e. 20 Ci/d). © 2013 IEEE.
Original languageEnglish
DOIs
Publication statusPublished - 2013
Externally publishedYes
Event2013 IEEE 25th Symposium on Fusion Engineering, SOFE 2013 - , United States
Duration: 1 Jan 2013 → …

Conference

Conference2013 IEEE 25th Symposium on Fusion Engineering, SOFE 2013
CountryUnited States
Period1/1/13 → …

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All Science Journal Classification (ASJC) codes

  • Software

Cite this

Franza, F., Boccaccini, L. V., Demange, D., Ciampichetti, A., & Zucchetti, M. (2013). Tritium permeation issues for helium-cooled breeding blankets. Paper presented at 2013 IEEE 25th Symposium on Fusion Engineering, SOFE 2013, United States. https://doi.org/10.1109/SOFE.2013.6635335