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Integrated design of breeding blanket and ancillary systems related to the use of helium or water as a coolant and impact on the overall plant design

Authors :
A. Del Nevo
Salvatore D’Amico
Pierluigi Chiovaro
Lorenzo Virgilio Boccaccini
F.R. Urgorri
Maria Teresa Porfiri
Antonio Froio
Alessia Santucci
Fabio Cismondi
Sergio Ciattaglia
Ion Cristescu
Silvano Tosti
A. Li Puma
R. Arredondo
Michael Rieth
C. Gliss
Robert Stieglitz
P.A. Di Maio
Matteo D’Onorio
David Rapisarda
G. Federici
Carlos Hugo Moreno
M. Coleman
F. Franza
E. Vallone
Ch. Day
J.C. Schwenzer
Marco Utili
I. Moscato
Pavel Pereslavtsev
Francisco A. Hernández
Gandolfo Alessandro Spagnuolo
Spagnuolo, G. A.
Arredondo, R.
Boccaccini, L. V.
Chiovaro, P.
Ciattaglia, S.
Cismondi, F.
Coleman, M.
Cristescu, I.
D'Amico, S.
Day, C.
Del Nevo, A.
Di Maio, P. A.
D'Onorio, M.
Federici, G.
Franza, F.
Froio, A.
Gliss, C.
Hernandez, F. A.
Li Puma, A.
Moreno, C.
Moscato, I.
Pereslavtsev, P.
Porfiri, M. T.
Rapisarda, D.
Rieth, M.
Santucci, A.
Schwenzer, J. C.
Stieglitz, R.
Tosti, S.
Urgorri, F. R.
Utili, M.
Vallone, E.
Spagnuolo G.A.
Arredondo R.
Boccaccini L.V.
Chiovaro P.
Ciattaglia S.
Cismondi F.
Coleman M.
Cristescu I.
D'Amico S.
Day C.
Del Nevo A.
Di Maio P.A.
D'Onorio M.
Federici G.
Franza F.
Froio A.
Gliss C.
Hernandez F.A.
Li Puma A.
Moreno C.
Moscato I.
Pereslavtsev P.
Porfiri M.T.
Rapisarda D.
Rieth M.
Santucci A.
Schwenzer J.C.
Stieglitz R.
Tosti S.
Urgorri F.R.
Utili M.
Vallone E.
Source :
Fusion engineering and design, 173, Article: 112933, Fusion Engineering and Design
Publication Year :
2021
Publisher :
Elsevier Ltd, 2021.

Abstract

Currently, for the EU DEMO, two Breeding Blankets (BBs) have been selected as potential candidates for the integration in the reactor. They are the Water Cooled Lithium Lead and the Helium Cooled Pebble Bed BB concepts. The two BB variants together with the associated ancillary systems drive the design of the overall plant. Therefore, a holistic investigation of integration issues derived by the BB and the installation of its ancillary systems has been performed. The issues related to the water activation due to the 16N and 17N isotopes and the impact on the primary heat transfer systems have been investigated providing guidelines and dedicated solution for the integration of safety devices as isolation valves. The tritium retention and the permeation rates through the blanket and its ancillary systems have been also assessed taking into account different operating points both for the BB and ancillaries and comparing, when possible, the releases with the operating and safety limits. Moreover, the issues related to the tritium start-up inventory as well as the uncertainties on the Tritium Breeding Ratio (TBR) due to the integration of the auxiliary systems within the Vacuum Vessel have been also studied. Finally, the impact of the BB concepts on the safety systems like the Vacuum Vessel Pressure Suppression System is described with a particular focus on the different measures that should be implemented according to the considered concept. All these aspects are then taken into account to drive future developments during the Concept Design Phase.<br />peer-reviewed

Details

Language :
English
ISSN :
09203796
Database :
OpenAIRE
Journal :
Fusion engineering and design, 173, Article: 112933, Fusion Engineering and Design
Accession number :
edsair.doi.dedup.....44cb4aaedbab23068c713872e15db98e