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

被引:101
|
作者
Hernandez, F. [1 ]
Pereslavtsev, P. [1 ]
Kang, Q. [1 ]
Norajitra, P. [1 ]
Kiss, B. [2 ]
Nadasi, G. [3 ]
Bitz, O. [1 ]
机构
[1] Inst Neutron Phys & Reactor Technol INR, Karlsruhe Inst Technol, Karlsruhe, Germany
[2] Budapest Univ Technol & Econ, Inst Nucl Techn, Budapest, Hungary
[3] Wigner Res Ctr Phys, Budapest, Hungary
关键词
HCPB; Breeding blanket; DEMO; TBR; REACTOR;
D O I
10.1016/j.fusengdes.2017.02.008
中图分类号
TL [原子能技术]; O571 [原子核物理学];
学科分类号
0827 ; 082701 ;
摘要
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 thermo-hydraulics and helium manifold systems. The former complex manifold backplates have been compacted and integrated in the cooling plates, releasing P-t1300 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 similar to 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. 2017 The Authors. Published by Elsevier B.V.
引用
收藏
页码:882 / 886
页数:5
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