Abstract
Within the framework of DEMO R&D activities, a research cooperation has been launched between ENEA-Brasimone, CEA-Saclay and the University of Palermo to investigate the thermo-mechanical behaviour of the outboard equatorial module of the DEMO1 Water-Cooled Lithium Lead (WCLL) blanket, both under normal operation and over-pressurization steady state scenarios. The research campaign has been carried out following a theoretical-computational approach based on the finite element method (FEM) and adopting a qualified commercial FEM code. In particular, two different three-dimensional FEM models of the WCLL blanket module have been set-up to be used for normal operation and over-pressurization analysis, respectively. The former reproduces realistically the WCLL blanket module central poloidal–radial region, including one breeder cell in the toroidal direction and all the five cells in the radial one. The latter simulates the entire module segment box, without including the breeder and its cooling tubes. Two set of uncoupled steady state thermo-mechanical analyses have been carried out with reference to the investigated loading scenarios. In particular, under normal operation scenario (level A) the module has been supposed to undergo both 15.5 MPa coolant pressure on its cooling channels walls and thermal deformations due to the flat-top plasma operational state thermal field, while under over-pressurization scenario (level D) it has been assumed to experience 15.5 MPa coolant pressure on its segment box internal walls while operating at normal operation thermal level. Results obtained are presented and critically discussed according to the SDC IC code.
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References
L. Giancarli, M. Dalle Donne, W. Dietz, Status of the European breeding blanket technology. Fusion Eng. Des. 36, 57–74 (1997)
M. Gasparotto, L.V. Boccaccini, L. Giancarli, S. Malang, Y. Poitevin, Demo blanket technology R&D results in EU. Fusion Eng. Des. 61–62, 263–271 (2002)
M.A. Fütterer, G. Benamati, L. Giancarli, G. Le Marois, A. Li Puma, Y. Poitevin et al., Further improvements of the water-cooled Pb-15.7Li blanket. Fusion Eng. Des. 58–59, 523–527 (2001)
P. Sardain, L. Giancarli, B. Michel, Y. Poitevin, A. Li Puma, J. Szczepanski, Power Plant Conceptual Study—Model A: Water Cooled Lithium Lead Concept. CEA report, NT—SERI—LFEA—12/5003
J. Aubert, G. Aiello, N. Jonquères, A. Li Puma, A. Morin, G. Rampal, Design Development of a DEMO Blanket Vertical Segment—Water-Cooled LiPb Concept. CEA report, DEN/DANS/DM2S/SEMT/BCCR/RT/13-003/A
G. Vella, P. Chiovaro, P.A. Di Maio, A. Li Puma, E. Oliveri, Neutronic and photonic analysis of the water-cooled Pb-17Li test blanket module for ITER-FEAT. Fusion Eng. Des. 61–62, 439–447 (2002)
P. Chiovaro, P.A. Di Maio, E. Oliveri, G. Vella, On the nuclear response of the water-cooled Pb-17Li Test Blanket Module for ITER-FEAT. Fusion Eng. Des. 69(1–4), 469–477 (2003)
P. Chiovaro, P.A. Di Maio, E. Oliveri, G. Vella, On the influence of the supporting frame on the nuclear response of the Helium-Cooled Lithium Lead Test Blanket Module for ITER. Fusion Eng. Des. 81(A), 677–686 (2006)
P. Chiovaro, P.A. Di Maio, E. Oliveri, G. Vella, A study of the potential influence of frame coolant on HCLL-TBM nuclear response. Fusion Eng. Des. 82, 2359–2365 (2007)
P. Chiovaro, P.A. Di Maio, E. Oliveri, G. Vella, On the effects of the supporting frame on the radiation-induced damage of HCLL-TBM structural material. J. Nucl. Mater. 367–370(1), 1344–1349 (2007)
M. Ciofalo, P.A. Di Maio, G. Sposito, G. Vella, Mixed MHD convection and Tritium transport in fusion-relevant configurations. Fusion Eng. Des. 75–79, 697–702 (2005)
I. Di Piazza, M. Ciofalo, MHD free convection in a liquid-metal filled cubic enclosure. II. Internal heating. Int. J. Heat Mass Transf. 45, 1493–1511 (2002)
S. Arcidiacono, M. Ciofalo, Low-Prandtl number natural convection in volumetrically heated rectangular enclosures III. Shallow cavity, AR = 0.25. Int. J. Heat Mass Transf. 44, 3053–3065 (2001)
P. Chiovaro, P.A. Di Maio, R. Giammusso, Q. Lupo, G. Vella, Thermal-mechanical and thermal-hydraulic integrated study of the Helium-Cooled Lithium Lead Test Blanket Module. Fusion Eng. Des. 85(7–9), 1147–1153 (2010)
ITER structural design criteria for in-vessel components (SDC-IC) code, G 74 MA 8 01-05-28 W 0.2, September 2012
A. Li Puma and WCLL/HCLL team, Specifications on Loading Conditions for WCLL/HCLL Blanket Design. EFDA report on WP12-DAS-02-T03 and WP12-DAS-02-T04, EFDA_D_2L3UJY, 2012
L.V. Boccaccini, L. Giancarli, G. Janeschitz, S. Hermsmeyer, Materials and design of the European DEMO blankets. J. Nucl. Mater. 329–333, 148–155 (2004)
F. Tavassoli, Fusion Demo Interim Structural Design Criteria (DISDC)/Appendix A Material Design Limit Data/A3.S18E Eurofer Steel, EFDA TASK TW4-TTMS-005-D01. CEA Report DMN/DIR/NT/2004-02/A, December 2004
Reference material data for the HCLL TBS, TBM-CA document D2-2009.002 V1.0, April 2009
A. Li Puma et alii, Potential and Limits of Water Cooled Divertor Concepts in View of Their Use for DEMO. CEA report SERMA/LPEC/RT/12-5272, pp. 17–20 (2012)
A.F. Tavassoli et al., Materials design for reduced activation martensitic steel type EUROFER. J. Nucl. Mater. 329–333, 257–262 (2004)
G. Aiello et al., Assessment of design limits and criteria requirements for EUROFER structures in TBM components. J. Nucl. Mater. 414, 53–68 (2011)
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Chiovaro, P., Arena, P., Aubert, J. et al. Assessment of the Thermo-mechanical Performances of a DEMO Water-Cooled Liquid Metal Blanket Module. J Fusion Energ 34, 277–292 (2015). https://doi.org/10.1007/s10894-014-9789-z
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DOI: https://doi.org/10.1007/s10894-014-9789-z