Pre-conceptual design of an encapsulated breeder commercial blanket for the STEP fusion reactor

被引:6
|
作者
Fradera, J. [1 ]
Sadaba, S. [1 ]
Calvo, F. [1 ]
Ha, S. [2 ]
Merriman, S. [2 ]
Gordillo, P. [3 ]
Connell, J. [3 ]
Elfaraskoury, A. [1 ]
Echeveste, B. [1 ]
机构
[1] IDOM, 1 St Ann St M2 7LR, Manchester, Lancs, England
[2] UKAEA, Culham Sci Ctr, Abingdon OX14 3DB, Oxon, England
[3] Univ Sheffield, Nucl AMRC, Adv Mfg Pk, Rotherham S60 5WG, S Yorkshire, England
基金
英国工程与自然科学研究理事会;
关键词
Fusion; STEP; Breeding blanket; Encapsulated fuel; Tritium; Self-sufficiency; Thermal-hydraulics; Mechanical; Neutronics; FLiBe; 1ST WALL; POWER; ACTIVATION; SYSTEM; CYCLE; HEAT;
D O I
10.1016/j.fusengdes.2021.112909
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
As part of the UKAEA Spherical Tokamak for Energy Production (STEP) fusion power station programme, a novel breeding blanket design was assessed. A conceptual design of STEP, which will be an innovative plan for a commercially-viable fusion power station, will be completed by 2024. The final aim of the current assessment is to find a pre-conceptual design that can be manufactured with existing techniques without compromising the fuel self-sufficiency, the heat removal and the shielding functions. The proposed concept, an starting point towards a commercial blanket design, is based on encapsulating the breeding material into hollow spheres forming a gas cooled packed bed. The generated tritium in the breeding material, as well as helium, will will be extracted from the pebbles and directly removed from the blanket by the cooling gas. A frontal multiplier as well as a back reflector have also been studied to maximize the tritium generation. This paper, which is a decided first step towards a breeding blanket for STEP, covers the material design properties and their compatibility, the design configuration, the neutronics analysis, the thermal-hydraulics analysis, a preliminary structural analysis, safety aspects and waste segregation and disposal.
引用
收藏
页数:15
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