A new HCPB breeding blanket for the EU DEMO: Evolution, rationale and preliminary performances
Autor: | Francisco Hernandez, Bela Kiss, Prachai Norajitra, P. Pereslavtsev, Qinlan Kang, O. Bitz, G. Nadasi |
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Rok vydání: | 2017 |
Předmět: |
Design modification
Technology Computer science Nuclear engineering Mass flow Mechanical Engineering Flow (psychology) Blanket 7. Clean energy 01 natural sciences 010305 fluids & plasmas law.invention Thermal hydraulics Breeder (animal) Materials Science(all) Nuclear Energy and Engineering law 0103 physical sciences General Materials Science 010306 general physics Manifold (fluid mechanics) ddc:600 Parametric statistics Civil and Structural Engineering |
Zdroj: | Fusion Engineering and Design Fusion engineering and design, 124, 882-886 |
ISSN: | 0920-3796 1873-7196 |
DOI: | 10.1016/j.fusengdes.2017.02.008 |
Popis: | 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. |
Databáze: | OpenAIRE |
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