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Neutronic analyses in support of the WCLL DEMO design development
- 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.
- Subjects :
- Neutron transport
Neutronic
Nuclear engineering
Blanket
7. Clean energy
01 natural sciences
010305 fluids & plasmas
Conceptual design
Neutron flux
Shielding
0103 physical sciences
MCNP
Nuclear
General Materials Science
Neutron
010306 general physics
DEMO
TBR
Civil and Structural Engineering
Mechanical Engineering
Nuclear data
Fusion power
WCLL
Nuclear Energy and Engineering
Electromagnetic shielding
Environmental science
Subjects
Details
- ISSN :
- 09203796
- Volume :
- 136
- Database :
- OpenAIRE
- Journal :
- Fusion Engineering and Design
- Accession number :
- edsair.doi.dedup.....4e0b6a27ffe69cceb1ddecb7c9fc01ef