Observatorio de I+D+i UPM

Descripción
Within the frame of the HiPER reactor, we propose and study a Self Cooled Lead Lithium blanket with two different cooling arrangements of the system First Wall ? Blanket for the HiPER reactor: Integrated First Wall Blanket and Separated First Wall Blanket. We compare the two arrangements in terms of power cycle efficiency, operation flexibility in out-off-normal situations and proper cooling and acceptable corrosion. The Separated First Wall Blanket arrangement is superior in all of them, and it is selected as the advantageous proposal for the HiPER reactor blanket. However, it still has to be improved from the standpoint of proper cooling and corrosion rates.
Internacional	Si
Nombre congreso	7th Inertial Fusion Science and Applications (ifsa 2011)
Tipo de participación	960
Lugar del congreso	Burdeos, FrancE
Revisores	Si
ISBN o ISSN	978-3-642-20532-3
DOI
Fecha inicio congreso	12/09/2011
Fecha fin congreso	16/09/2011
Desde la página	1
Hasta la página	4
Título de las actas	Proceedings of the Conference

Esta actividad pertenece a memorias de investigación

• Autor: Rafael Juarez Mañas (UPM)
• Autor: J. Sanz (UNED)
• Autor: C. Sánchez (UNED)
• Autor: C. Zanzi (UNED)
• Autor: J. Hernández (UNED)
• Autor: Jose Manuel Perlado Martin (UPM)

• Creador: Grupo de Investigación: Fusión Nuclear Inercial y Tecnología de fusión
• Centro o Instituto I+D+i: Instituto de Fusión Nuclear
• Departamento: Ingeniería Nuclear