Instrumentation integration in the European Test Blanket Modules

被引:0
|
作者
Rodriguez-Lopez, Eduardo [1 ]
Alonso, David [1 ]
Dominguez, Victor [1 ]
Maqueda, Luis [1 ]
Nunez, Celia [1 ]
Rueda, Fernando [1 ]
Vallory, Joelle [2 ]
Forte, Ruggero [3 ]
Fantini, Francesca [2 ]
Ricapito, Italo [4 ]
Poitevin, Yves [4 ]
机构
[1] Esteyco Mech, Avda Burgos 12-B Bajo, Madrid 28036, Spain
[2] Fus Energy, Josep Pla 2,Torres Diagonal Litoral B3, Barcelona 08019, Spain
[3] ATG Sci & Engn, Plaza Ernest Lluch i Marti 5, Barcelona 08019, Spain
[4] Fus Energy, P58 F4E Off, 82-P58 F4E Off,Route Vinon Sur Verdon, F-13115 Verdon, France
关键词
Instrumentation integration; Test Blanket Module; Reconstruction algorithms; Sensor optimization;
D O I
10.1016/j.fusengdes.2024.114374
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
Amongst the four different Test Blanket Modules (TBM) that shall be tested in ITER, the European domestic agency (Fusion For Energy) participates in two concepts: the Water-Cooled Lithium Lead (WCLL) and the Helium-Cooled Ceramic Pebbles (HCCP). A progressive set of activities including implementation and integration of instrumentation has been conducted from preliminary design stage. The current work is mainly focused on the thermal and mechanical instrumentation, although other sensors are also considered. The integration of instrumentation in the TBMs is challenging; consequently, the number and position of the sensors should be carefully optimized. An important advance of the current work is the use of reconstruction algorithms to provide an estimation of the reconstruction ability of the different sensor sets. These algorithms comprise a series of mathematical tools which use model results and sensor measurements to infer different variables at positions where no in-situ measurement is available. Apart from the use of these algorithms, the final decision on sensor location has been conducted from a holistic point of view considering the different perspectives and integration challenges.
引用
收藏
页数:6
相关论文
共 50 条
  • [41] The European Breeding Blanket Test Facility: An integrated device to test European helium cooled TBMs in view of ITER
    Utili, M.
    Tincani, A.
    Aiello, A.
    Ricapito, I.
    Coccoluto, G.
    FUSION ENGINEERING AND DESIGN, 2009, 84 (7-11) : 1881 - 1886
  • [42] System engineering approach in the EU Test Blanket Systems Design Integration
    Panayotov, D.
    Sardain, P.
    Boccaccini, L. V.
    Salavy, J. -F.
    Cismondi, F.
    Jourd'Heuil, L.
    FUSION ENGINEERING AND DESIGN, 2011, 86 (9-11) : 2241 - 2245
  • [43] Test Blanket Module Pipe Forest integration in ITER equatorial port
    Commin, L.
    Madeleine, S.
    Dechelle, C.
    Patterlini, J. -C.
    Doceul, L.
    Rampal, G.
    Cismondi, F.
    Bede, O.
    FUSION ENGINEERING AND DESIGN, 2011, 86 (9-11) : 2143 - 2147
  • [44] Review of accidental safety studies for the European HCPB test blanket system
    Boccaccini, L. V.
    Ciattaglia, S.
    Meyder, R.
    Jin, X.
    NUCLEAR FUSION, 2007, 47 (07) : S436 - S441
  • [45] ITER fast ion confinement in the presence of the European test blanket module
    Akaslompolo, Simppa
    Kurki-Suonio, Taina
    Asunta, Otto
    Cavinato, Mario
    Gagliardi, Mario
    Hirvijoki, Eero
    Saibene, Gabriella
    Sipila, Seppo
    Snicker, Antti
    Sarkimaki, Konsta
    Varje, Jari
    NUCLEAR FUSION, 2015, 55 (09)
  • [46] Low activation steels welding with PWHT and coating for ITER test blanket modules and DEMO
    Aubert, P.
    Tavassoli, F.
    Rieth, M.
    Diegele, E.
    Poitevin, Y.
    JOURNAL OF NUCLEAR MATERIALS, 2011, 409 (02) : 156 - 162
  • [47] Finalization of the conceptual design of the auxiliary circuits for the European test blanket systems
    Aiello, A.
    Ghidersa, B. E.
    Utili, M.
    Vala, L.
    Ilkei, T.
    Di Gironimo, G.
    Mozzillo, R.
    Tarallo, A.
    Ricapito, I.
    Calderoni, P.
    FUSION ENGINEERING AND DESIGN, 2015, 96-97 : 56 - 63
  • [48] FUNCTIONAL INSTRUMENTATION MODULES
    JOERGER, FA
    KLAISNER, LA
    IEEE TRANSACTIONS ON INDUSTRY APPLICATIONS, 1975, 11 (06) : 713 - 715
  • [49] A path to stable low-torque plasma operation in ITER with test blanket modules
    Lanctot, M. J.
    Snipes, J. A.
    Reimerdes, H.
    Paz-Soldan, C.
    Logan, N.
    Hanson, J. M.
    Buttery, R. J.
    deGrassie, J. S.
    Garofalo, A. M.
    Gray, T. K.
    Grierson, B. A.
    King, J. D.
    Kramer, G. J.
    La Haye, R. J.
    Pace, D. C.
    Park, J. -K.
    Salmi, A.
    Shiraki, D.
    Strait, E. J.
    Solomon, W. M.
    Tala, T.
    Van Zeeland, M. A.
    NUCLEAR FUSION, 2017, 57 (03)
  • [50] Review of candidate welding processes of RAFM steels for ITER test blanket modules and DEMO
    Aubert, P.
    Tavassoli, F.
    Rieth, M.
    Diegele, E.
    Poitevin, Y.
    JOURNAL OF NUCLEAR MATERIALS, 2011, 417 (1-3) : 43 - 50