Studies of a Self Cooled Lead Lithium blanket for HiPER Reactor


Autoria(s): Juarez Mañas, Rafael; Sanz Gonzalo, Javier; Sánchez, C.; Zanzi, C.; Hernández, J.; Perlado Martin, Jose Manuel
Data(s)

2011

Resumo

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

Formato

application/pdf

Identificador

http://oa.upm.es/13004/

Idioma(s)

eng

Publicador

E.T.S.I. Industriales (UPM)

Relação

http://oa.upm.es/13004/1/INVE_MEM_2011_108722.pdf

http://www.ifsa11.org/

info:eu-repo/semantics/altIdentifier/doi/null

Direitos

http://creativecommons.org/licenses/by-nc-nd/3.0/es/

info:eu-repo/semantics/openAccess

Fonte

Proceedings of the 7th Conference on Inertial Fusion Sciences and Applications, IFSA 2011 | 7th Conference on Inertial Fusion Sciences and Applications, IFSA 2011 | 12/09/2011 - 16/09/2011 | Burdeos, Francia

Palavras-Chave #Energía Nuclear #Ingeniería Industrial
Tipo

info:eu-repo/semantics/conferenceObject

Ponencia en Congreso o Jornada

PeerReviewed