Designs and technologies for plasma-facing wall protection in EU DEMO

被引:20
作者
Barrett, T. R. [1 ]
Chuilon, B. [1 ]
Kovari, M. [1 ]
Hernandez, D. Leon [1 ]
Richiusa, M. L. [1 ]
Adame, E. Rosa [1 ]
Tivey, R. [1 ]
Vizvary, Z. [1 ]
Xue, Y. [1 ]
Maviglia, F. [2 ]
机构
[1] Culham Sci Ctr, CCFE, Abingdon OX14 3DB, Oxon, England
[2] EUROfus Consortium, PPPT Dept, Boltzmannstr 2, Garching, Germany
基金
英国工程与自然科学研究理事会;
关键词
DEMO reactor; plasma-facing components; limiter engineering design; critical heat flux; PFC engineering; wall protection; SIMULATIONS; PROGRESS;
D O I
10.1088/1741-4326/ab085b
中图分类号
O35 [流体力学]; O53 [等离子体物理学];
学科分类号
070204 ; 080103 ; 080704 ;
摘要
The EU DEMO plasma is almost completely enveloped by large breeding blanket segments for tritium breeding and power extraction. Shaping of the blanket plasma-facing wall in 3D may prove to be essential, but this strategy alone is not sufficient to protect against anticipated transient plasma events. The high heat flux wall-limiter approach used in ITER is not thought to be viable in a tritium self-sufficient power reactor, and so in EU DEMO wall protection using discrete limiters is pursued. Two types of discrete limiter are described in this paper. One is an equatorial port limiter designed to handle the power during the plasma start-up phase, making use of water-cooled tungsten/CuCrZr monoblock technology. The second is the upper limiter, featuring a plasma-facing component designed specifically for extreme transient loading due to a vertical displacement event. The heat flux channelling and thermal barrier features of this design are shown to considerably reduce CuCrZr pipe temperature, and so reduce the likelihood of catastrophic failure. A preliminary neutronic calculation has shown that the impact of these discrete limiters on overall tritium breeding ratio is relatively low.
引用
收藏
页数:8
相关论文
共 26 条
  • [1] [Anonymous], 2018, JEFF 3 3 JOINT EVALU
  • [2] Enhancing the DEMO divertor target by interlayer engineering
    Barrett, T. R.
    McIntosh, S. C.
    Fursdon, M.
    Hancock, D.
    Timmis, W.
    Coleman, M.
    Rieth, M.
    Reiser, J.
    [J]. FUSION ENGINEERING AND DESIGN, 2015, 98-99 : 1216 - 1220
  • [3] Objectives and status of EUROfusion DEMO blanket studies
    Boccaccini, L. V.
    Aiello, G.
    Aubert, J.
    Bachmann, C.
    Barrett, T.
    Del Nevo, A.
    Demange, D.
    Forest, L.
    Hernandez, F.
    Norajitra, P.
    Porempovic, G.
    Rapisarda, D.
    Sardain, P.
    Utili, M.
    Vala, L.
    [J]. FUSION ENGINEERING AND DESIGN, 2016, 109 : 1199 - 1206
  • [4] Design and manufacturing of the ITER limiter
    Cardella, A
    Skladnov, K
    Ioki, K
    Pacher, H
    Strebkov, Y
    Daenner, W
    [J]. FUSION ENGINEERING AND DESIGN, 2002, 61-62 : 111 - 116
  • [5] Preliminary investigation on W foams as protection strategy for advanced FW PFCs
    De Luca, Riccardo
    Maviglia, Francesco
    Federic, Gianfranco
    Calabro, Giuseppe
    Fanelli, Pierluigi
    Vivio, Francesco
    [J]. FUSION ENGINEERING AND DESIGN, 2019, 146 : 1690 - 1693
  • [6] WCLL breeding blanket design and integration for DEMO 2015: status and perspectives
    Del Nevo, A.
    Martelli, E.
    Agostini, P.
    Arena, P.
    Bongiovi, G.
    Caruso, G.
    Di Gironimo, G.
    Di Maio, P. A.
    Eboli, M.
    Giammusso, R.
    Giannetti, F.
    Giovinazzi, A.
    Mariano, G.
    Moro, F.
    Mozzillo, R.
    Tassone, A.
    Rozzia, D.
    Tarallo, A.
    Tarantino, M.
    Utili, M.
    Villari, R.
    [J]. FUSION ENGINEERING AND DESIGN, 2017, 124 : 682 - 686
  • [7] Simulations of ITER start-up and assessment of limiter power loads
    Federici, G.
    Zolotukhin, O.
    Kobayashi, M.
    Loarte, A.
    Strohmayer, G.
    Tanga, A.
    Portone, A.
    Horton, L.
    Feng, Y.
    Sardei, F.
    Gribov, Y.
    Shimada, M.
    Polevoi, A.
    Mitteau, R.
    Lowry, C.
    [J]. JOURNAL OF NUCLEAR MATERIALS, 2007, 363 : 346 - 352
  • [8] DEMO design activity in Europe: Progress and updates
    Federici, G.
    Bachmann, C.
    Barucca, L.
    Biel, W.
    Boccaccini, L.
    Brown, R.
    Bustreo, C.
    Ciattaglia, S.
    Cismondi, F.
    Coleman, M.
    Corato, V.
    Day, C.
    Diegele, E.
    Fischer, U.
    Franke, T.
    Gliss, C.
    Ibarra, A.
    Kembleton, R.
    Loving, A.
    Maviglia, F.
    Meszaros, B.
    Pintsuk, G.
    Taylor, N.
    Tran, M. Q.
    Vorpahl, C.
    Wenninger, R.
    You, J. H.
    [J]. FUSION ENGINEERING AND DESIGN, 2018, 136 : 729 - 741
  • [9] A hybrid analysis procedure enabling elastic design rule assessment of monoblock-type divertor components
    Fursdon, M.
    You, J-H
    Barrett, T.
    Li, M.
    [J]. FUSION ENGINEERING AND DESIGN, 2018, 135 : 154 - 164
  • [10] Thermophysical properties of Cu-ZrO2 composites as potential thermal barrier materials for a DEMO W-monoblock divertor
    Galatanu, Magdalena
    Enculescu, Monica
    Galatanu, Andrei
    [J]. FUSION ENGINEERING AND DESIGN, 2018, 127 : 179 - 184