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Neutronic analyses in support of the WCLL DEMO design development

Authors :
Rosaria Villari
Simone Noce
Davide Flammini
Fabio Moro
Alessandro Del Nevo
Emanuela Martelli
Rocco Mozzillo
Moro, F.
Del Nevo, A.
Flammini, D.
Martelli, E.
Mozzillo, R.
Noce, S.
Villari, R.
Source :
Fusion Engineering and Design
Publication Year :
2018
Publisher :
Elsevier BV, 2018.

Abstract

In the frame of the EUROfusion Consortium programme, the Water Cooled Lithium Lead (WCLL) option has been chosen as a candidate for the breeding blanket (BB) of the European fusion power demonstration plant (DEMO) conceptual design. Neutronic analyses play a fundamental role in the development of the WCLL blanket, providing guidelines for its design based on the evaluation of the nuclear performances. A detailed three-dimensional MCNP model of the latest WCLL layout has been generated and integrated in a DEMO MCNP generic model suitably designed for neutronic analyses. Three-dimensional neutron and gamma transport simulations have been performed using the MCNP5v1.6 Monte Carlo code and JEFF 3.2 nuclear data libraries, in order to assess the WCLL-DEMO tritium self-sufficiency and the shielding capabilities of the breeding blanket/manifold system to protect the vacuum vessel and toroidal field coils. Furthermore, radial profiles of the neutron flux, nuclear heating, neutron damage and he-production have been assessed in the inboard and outboard equatorial planes. The outcome of the present study highlights the potential and suitability of the WCLL breeding blanket for the application to DEMO, both in terms of tritium production and shielding performances.

Details

ISSN :
09203796
Volume :
136
Database :
OpenAIRE
Journal :
Fusion Engineering and Design
Accession number :
edsair.doi.dedup.....4e0b6a27ffe69cceb1ddecb7c9fc01ef