Advancements in the Helium-Cooled Pebble Bed Breeding Blanket for the EU DEMO: Holistic Design Approach and Lessons Learned

被引:54
作者
Hernandez, Francisco A. [1 ]
Pereslavtsev, Pavel [1 ]
Zhou, Guangming [1 ]
Kiss, Bela [2 ]
Kang, Qinlan [1 ]
Neuberger, Heiko [1 ]
Chakin, Vladimir [1 ]
Gaisin, Ramil [1 ]
Vladimirov, Pavel [1 ]
Boccaccini, Lorenzo V. [1 ]
Spagnuolo, Gandolfo A. [1 ]
D'Amico, Salvatore [1 ]
Moscato, Ivo [3 ]
机构
[1] Karlsruhe Inst Technol, D-76344 Eggenstein Leopoldshafen, Baden Wurttembe, Germany
[2] Budapest Univ Technol & Econ, H-1111 Budapest, Hungary
[3] Univ Palermo, I-90133 Palermo, Italy
关键词
Helium-cooled pebble bed; DEMO; fuel-breeder pin; tritium breeding; tritium breeding ratio; 1ST WALL; PROGRESS;
D O I
10.1080/15361055.2019.1607695
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) blanket is one of the two concepts proposed as a driver blanket for the European Union Demonstration Fusion Power Reactor (EU DEMO). In contrast to past conceptual design studies, in the frame of the current Power Plant Physics and Technology of the EUROfusion Consortium, the ongoing EU DEMO preconceptual design activities have adopted a holistic and integrated (i.e., systems engineering) design approach. As a consequence of this new approach, many interfaces and requirements have been identified, some of them driving the design of the blankets. This paper shows the advancements in the HCPB breeding blanket and describes the lessons learned after implementing the new approach. This new set of requirements has led us to reconsider fundamental aspects of the HCPB blanket design, especially in the way of how the heat is extracted from the blanket. Among others, the requirement to achieve a mature balance of plant (BOP) system plays a central role as a key design driver and has forced us to reduce pressure drops in the breeding blanket. In this regard, the blanket has been redesigned, leading to an enhanced concept based on single-module segments with a hexagonal matrix of fuel-breeder pins. Both the fuel-breeder pins and the first wall (FW) are equipped with turbulence promoters (augmented wall roughness in the fuel-breeder pins and V-ribs in the FW), following a similar idea as in the past MAGNOX, Advanced Gas Reactor (AGR), and Gas Cooled Reactor (GCR) programs in fission. This has led to minimizing the pressure drops while maximizing the heat transfer. Also, the blanket outlet temperature has been extended to 520 degrees C, following the same principle as in Generation IV's GCRs of maximizing the temperature difference across the core to minimize the reactor mass flow rate and thus the circulating power. All these features have led to a remarkably low plant circulating power (80 to 90MW) and the required power per helium blower (5 to 6MW), which potentially solves the key long-standing problem of the BOP technology readiness level for an approximate to 2.4-GW(thermal) helium-cooled DEMO reactor.
引用
收藏
页码:352 / 364
页数:13
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