Published October 2014 | Version v1
Journal article

Development of the breeding blanket and shield model for the fusion power reactors system SYCOMORE

  • 1. CEA, DEN, Saclay, DM2S, SERMA, F-91191 Gif-sur-Yvette (France)
  • 2. Incka, 19-21 Rue du 8 mai 1945, F-94110 Arcueil (France)

Description

SYCOMORE, a fusion reactor system code based on a modular approach is under development at CEA. Within this framework, this paper describes the relevant sub-modules which have been implemented to model the main outputs of the breeding blanket and shield block of the system code: tritium breeding ratio, peak energy deposition in toroidal field coils, reactor layout and power deposition, blanket pressure drops and materials inventory. Blanket and shield requirements are calculated by several sub-modules: the blanket assembly and layout sub-module, the neutronic sub-module, the blanket design sub-module (thermal hydraulic and thermo-mechanic pre-design tool). A power flow module has also been developed which is directly linked to the blanket thermo-dynamic performances, which is not described in this paper. For the blanket assembly and layout and the blanket module design sub-modules, explicit analytic models have been developed and implemented; for the neutronic sub-module neural networks that replicate the results of appropriate simplified 1D and 2D neutronic simulations have been built. Presently, relevant model for the Helium Cooled Lithium Lead is available. Sub-modules have been built in a way that they can run separately or coupled into the breeding blanket and shield module in order to be integrated in SYCOMORE. In the paper, the objective and main input/output parameters of each sub-module are reported and relevant models discussed. The application to previous studied reactor models (PPCS model AB, DEMO-HCLL 2006–2007 studies) is also presented

Availability note (English)

Available from http://dx.doi.org/10.1016/j.fusengdes.2014.04.058

Additional details

Identifiers

DOI
10.1016/j.fusengdes.2014.04.058;
PII
S0920-3796(14)00335-4;

Publishing Information

Journal Title
Fusion Engineering and Design
Journal Volume
89
Journal Issue
7-8
Journal Page Range
p. 1195-1200
ISSN
0920-3796
CODEN
FEDEEE

Conference

Title
11. international symposium on fusion nuclear technology
Acronym
ISFNT-11
Dates
15-20 Sep 2013
Place
Barcelona (Spain)

Optional Information

Copyright
Copyright (c) 2014 Elsevier Science B.V., Amsterdam, The Netherlands, All rights reserved.