Title :
Tritium diffusion challenges on future nuclear fusion reactors
Author :
Moral, Nuria ; Gonzalez-del Moral, Octavio ; Garoz, David ; Alvarez, J. ; Perlado, J.M.
Author_Institution :
Inst. de Fusion Nucl., Univ. Politec. de Madrid, Madrid, Spain
Abstract :
Diffusion and retention processes of hydrogen isotopes and helium are a key issue in order to construct a successful nuclear fusion reactor for both magnetic confinement fusion (MCF) and inertial confinement fusion (ICF). The tritium self-sufficiency of the fusion reactor depends on an efficient tritium extraction protocol. Transport phenomena of hydrogen isotopes through the vacuum vessel, Breeding Blanket, and Tritium Plant components are complex and involve many physical properties. Retention of light species and evolution of defects in the first wall and structural components is a major threat to their performance and operational lifetime. Diffusion parameters need to be understood and accurately assessed to design an economic and safety fuel cycle. This report is an overview on what researchers are facing up while working on hydrogen isotopes and helium diffusion aspects. A summary of transport challenges in the different components of the fusion reactors will be outlined. Also, experimental and computational simulation needs encountered during the elaboration of this work will also be described.
Keywords :
fusion reactor blankets; fusion reactor design; fusion reactor safety; plasma inertial confinement; plasma toroidal confinement; plasma transport processes; tritium handling; ICF; MCF; breeding blanket; computational simulation; defect evolution; diffusion parameters; economic fuel cycle design; efficient tritium extraction protocol; experimental simulation; first wall component; fusion reactor components; future nuclear fusion reactors; helium diffusion aspects; helium isotope; hydrogen isotope transport phenomena; hydrogen isotopes; inertial confinement fusion; light species retention; magnetic confinement fusion; operational lifetime; performance lifetime; physical properties; retention process; safety fuel cycle design; structural component; transport challenges; tritium diffusion challenges; tritium plant components; tritium self-sufficiency; vacuum vessel; Fuels; Fusion reactors; Helium; Hydrogen; Inductors; Isotopes; diffusion; fuel cycle; fusion; helium; hydrogen isotopes; transport; tritium;
Conference_Titel :
Fusion Engineering (SOFE), 2013 IEEE 25th Symposium on
Conference_Location :
San Francisco, CA
Print_ISBN :
978-1-4799-0169-2
DOI :
10.1109/SOFE.2013.6635392