An update on the latest and most relevant improvements achieved in the European helium-cooled ceramic breeder TBM design

被引:2
|
作者
Rueda, F. [1 ]
Maqueda, L. [1 ]
Dominguez, V. [1 ]
Rodriguez, E. [1 ]
Alonso, D. [1 ]
Nunez, C. [1 ]
Vallory, J. [2 ]
Poitevin, Y. [3 ]
Fantini, F. [2 ]
机构
[1] ESTEYCO Mech, Ave Burgos,12B Bajo, Madrid 28036, Spain
[2] Fus Energy, Josep Pla 2,Torres Diagonal Litoral B3, Barcelona 08019, Spain
[3] Fus Energy, 82-P58 F4E Off,Route Vinon Sur Verdon, F-13115 St Paul Les Durance, France
关键词
ITER; Tritium breeding; Test blanket modules; Advanced design; Design by analysis;
D O I
10.1016/j.fusengdes.2023.113660
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 European TBM (Test Blanket Module) program under development will test two alternative concepts for tritium generation and extraction in ITER: a helium cooled / ceramic pebble breeder concept and a water cooled / lithium lead breeder concept. The former implements Advanced Ceramic Breeder pebbles that act as tritium breeding material, and Beryl-lium pebbles as neutron multiplier. A Reduced Activation Ferritic Martensitic steel, the EUROFER-97 (X10CrWVTa9-1), is used as structural material and pressurized Helium technology is implemented for effi-cient heat extraction (300-500 degrees C, 8 MPa). The design of the TBM box involves challenges that must be tackled with a holistic approach to simultaneously consider a variety of aspects. Some of these challenges include: the thermal performance and the structural integrity of the TBM under ITER normal operations and accidental conditions, the implementation of pressurized equipment regulation(s), the convergence with manufacturing activities being developed in parallel and the high congestion in the reduced TBM volume -especially when considering instrumentation integration- without affecting too much the tritium breeding capability. It is also key to develop advanced methodologies based on design by analysis to virtually test alternative design solutions in an agile manner. These should be linked to the applicable nuclear design code (RCC-MRx) to consolidate design choices. In this way, a traceable evolution of the TBM design process can be built where alternatives are tested, compared and either discarded or selected in a consistent and comprehensive framework. This paper presents an overview of the very significant progress achieved in the design of the helium cooled concept TBM over the last two years, a period that corresponds to the first steps of the preliminary design phase towards the Preliminary Design Review (PDR) gate. This includes a significant change in the design of the back manifold area and the connection with the rest of the TBM-Set that solves long-standing historical problems inherited from pre-conceptual design stage. An update on the latest and most relevant methodological de-velopments achieved is also provided in this paper, since these have been key to progress with the design evolutions in a sound and traceable manner. To end, the paper also presents some examples of the instrumen-tation definition and its complex integration within and outside the TBM box.
引用
收藏
页数:12
相关论文
共 34 条
  • [1] Progress on design and R&D for helium-cooled ceramic breeder TBM in China
    Feng, K. M.
    Pan, C. H.
    Zhang, G. S.
    Luo, T. Y.
    Zhao, Z.
    Chen, Y. J.
    Feng, Y. J.
    Ye, X. F.
    Hu, G.
    He, K. H.
    Niu, R. W.
    Li, Z. X.
    Wang, P. H.
    Xiang, B.
    Zhang, L.
    Wang, Q. J.
    Zhao, F. C.
    Cao, Q. X.
    Wang, F.
    Yuan, T.
    Zheng, G. Y.
    Liu, Y.
    Zhong, Y.
    Zhang, M. C.
    FUSION ENGINEERING AND DESIGN, 2012, 87 (7-8) : 1138 - 1145
  • [2] CONCEPTUAL DESIGN OF A HELIUM-COOLED CERAMIC BREEDER BLANKET FOR CFETR
    Lei, Mingzhun
    Song, Yuntao
    Ye, Minyou
    Lu, Kun
    Pei, Kun
    Xu, Kun
    Xu, Shuling
    FUSION SCIENCE AND TECHNOLOGY, 2015, 68 (04) : 772 - 779
  • [3] Safety assessment of Chinese ITER TBM design with helium-cooled solid breeder concept
    Chen, Zhi
    Feng, K. M.
    Zhou, Z. W.
    Gao, C. M.
    Luo, D. L.
    Yuan, T.
    Xie, H.
    Liu, H. B.
    NUCLEAR FUSION, 2007, 47 (07) : S442 - S446
  • [4] A HELIUM-COOLED, POLOIDAL BLANKET WITH CERAMIC BREEDER AND BERYLLIUM MULTIPLIER FOR THE NEXT EUROPEAN TORUS
    DONNE, MD
    FISCHER, U
    KUCHLE, M
    NUCLEAR TECHNOLOGY, 1985, 71 (01) : 15 - 28
  • [5] DEVELOPMENT OF A THERMAL-HYDRAULIC CODE FOR CHINESE HELIUM-COOLED CERAMIC BREEDER TBM COOLING SYSTEM
    Wang, Jie
    Su, Guanghui
    Tian, Wenxi
    Qiu, Suizheng
    PROCEEDINGS OF THE 21ST INTERNATIONAL CONFERENCE ON NUCLEAR ENGINEERING - 2013, VOL 5, 2014,
  • [6] TRANSIENT FLOW BEHAVIOR FOR A HELIUM-COOLED CERAMIC BREEDER BLANKET
    YING, AY
    RAFFRAY, AR
    ABDOU, MA
    NUCLEAR ENGINEERING AND DESIGN, 1991, 126 (01) : 137 - 145
  • [7] Preliminary Design of a Helium-Cooled Ceramic Breeder Blanket for CFETR Based on the BIT Concept
    Ma Xuebin
    Liu Songlin
    Li Jia
    Pu Yong
    Chen Xiangcun
    PLASMA SCIENCE & TECHNOLOGY, 2014, 16 (04) : 390 - 395
  • [8] Preliminary Design of a Helium-Cooled Ceramic Breeder Blanket for CFETR Based on the BIT Concept
    马学斌
    刘松林
    李佳
    蒲勇
    陈香存
    Plasma Science and Technology, 2014, 16 (04) : 390 - 395
  • [9] Preliminary Design of a Helium-Cooled Ceramic Breeder Blanket for CFETR Based on the BIT Concept
    马学斌
    刘松林
    李佳
    蒲勇
    陈香存
    Plasma Science and Technology, 2014, (04) : 390 - 395
  • [10] Progress of optimization and modification of China ITER helium-cooled solid breeder TBM
    Zhang, Guo-Shu
    Feng, Kai-Ming
    Hedongli Gongcheng/Nuclear Power Engineering, 2010, 31 (SUPPL. 2): : 107 - 110