A new HCPB breeding blanket for the EU DEMO: evolution, rationale and preliminary performances

Abstract The Helium Cooled Pebble Bed (HCPB) Breeding Blanket (BB) is one of the 4 BB concepts being investigated in the EU for their possible implementation in DEMO. During 2014 the former “beer-box” BB concept based on the ITER’s HCPB Test Blanket Module suffered several design changes so as to meet the different counteracting nuclear, thermohydraulic and thermomechanical requirements. These studies evidenced that the concept is too rigid to meet the tight TBR requirements imposed for the EU DEMO (i.e. TBR ≥ 1.10). Additionally, the complex manifold system with unbalanced helium mass flow in each of the 2 parallel cooling loops made the concept thermohydraulically complex. However, parametric studies during 2015 revealed that the HCPB concept have potential for a better nuclear performance, as well as margin for a significant simplification of the cooling internals by redefining the cooling plates and the architecture of the blanket, building a symmetric flow scheme. This paper describes the new HCPB concept based on an integrated FW with the breeding zone thermohydraulics and helium manifold systems. The former complex manifold backplates have been compacted and integrated in the cooling plates, releasing ≈300 mm of radial space that can be used now to increase breeder zone, the neutron shielding, to reinforce the Back Supporting Structure (BSS) or basically to reduce the reactor size. Detailed neutronic analyses have yielded a TBR of ∼1.20 for the baseline design. Initial analyses show a correct thermohydraulic behavior. Preliminary thermomechanical analyses also indicate that the design can potentially withstand an in-box LOCA at 9 MPa at a level C according to the RCC-MRx code. Future consolidation activities are described, which shall lead to a concept meeting the BB requirements.

[1]  Francisco Hernandez,et al.  Thermo-mechanical analyses and assessment with respect to the design codes and standards of the HCPB-TBM Breeder Unit , 2012 .

[2]  Ulrich Fischer,et al.  Neutronic analyses for the optimization of the advanced HCPB breeder blanket design for DEMO , 2017 .

[3]  Lorenzo V. Boccaccini,et al.  Preliminary steady state and transient thermal analysis of the new HCPB blanket for EU DEMO reactor , 2016 .

[4]  F. Franza,et al.  Requirements for helium cooled pebble bed blanket and R&D activities , 2014 .

[5]  Ulrich Fischer,et al.  Non-linear failure analysis of HCPB blanket for DEMO taking into account high dose irradiation , 2014 .

[6]  W. Nägele,et al.  European DEMO BOT Solid Breeder Blanket , 1994 .

[7]  Massimiliano Mattei,et al.  Initial DEMO tokamak design configuration studies , 2015 .

[8]  Marc Kamlah,et al.  Effective thermal conductivity of advanced ceramic breeder pebble beds , 2017 .

[9]  Christian Bachmann,et al.  Neutronic analyses of design issues affecting the tritium breeding performance in different DEMO blanket concepts , 2016 .

[10]  M. Coleman,et al.  On the EU approach for DEMO architecture exploration and dealing with uncertainties , 2016 .

[11]  E. Bogusch,et al.  DEMO-relevant test blankets for NET/ITER. I : Self-cooled liquid metal breeder blanket , 1991 .

[12]  H. Neuberger,et al.  Manufacturing pre-qualification of a Short Breeder Unit mockup (SHOBU) as part of the roadmap toward the out-of-pile validation of a full scale Helium Cooled Pebble Bed Breeder Unit , 2015 .

[13]  D. P. Luigi,et al.  DEMO and fusion power plant conceptual studies in Europe , 2006 .

[14]  Lorenzo V. Boccaccini,et al.  Preliminary structural analysis of the new HCPB blanket for EU DEMO reactor , 2016 .

[15]  E. Diegele,et al.  The development of EUROFER reduced activation steel , 2003 .