Studies of a Self Cooled Lead Lithium blanket for HiPER Reactor

Juarez Mañas, Rafael and Sanz Gonzalo, Javier and Sánchez, C. and Zanzi, C. and Hernández, J. and Perlado Martín, José Manuel (2011). Studies of a Self Cooled Lead Lithium blanket for HiPER Reactor. In: "7th Conference on Inertial Fusion Sciences and Applications, IFSA 2011", 12/09/2011 - 16/09/2011, Burdeos, Francia. pp. 1-4.

Description

Title: Studies of a Self Cooled Lead Lithium blanket for HiPER Reactor
Author/s:
  • Juarez Mañas, Rafael
  • Sanz Gonzalo, Javier
  • Sánchez, C.
  • Zanzi, C.
  • Hernández, J.
  • Perlado Martín, José Manuel
Item Type: Presentation at Congress or Conference (Article)
Event Title: 7th Conference on Inertial Fusion Sciences and Applications, IFSA 2011
Event Dates: 12/09/2011 - 16/09/2011
Event Location: Burdeos, Francia
Title of Book: Proceedings of the 7th Conference on Inertial Fusion Sciences and Applications, IFSA 2011
Date: 2011
Subjects:
Faculty: E.T.S.I. Industriales (UPM)
Department: Ingeniería Nuclear [hasta 2014]
Creative Commons Licenses: Recognition - No derivative works - Non commercial

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Abstract

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

More information

Item ID: 13004
DC Identifier: http://oa.upm.es/13004/
OAI Identifier: oai:oa.upm.es:13004
Official URL: http://www.ifsa11.org/
Deposited by: Memoria Investigacion
Deposited on: 07 Nov 2012 09:54
Last Modified: 07 Sep 2017 18:10
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