Armor Thickness Assessment for the Divertor Tokamak Test Facility (DTT) Divertor Targets

被引:1
|
作者
Roccella, Selanna [1 ]
Giorgetti, F. [1 ,2 ]
De Luca, R. [1 ]
De Sano, G. [3 ]
Dose, G. [3 ]
Innocente, P. [4 ]
Lorusso, P. [1 ]
Polli, G. M. [1 ,2 ]
Riccardi, B. [2 ]
Greuner, H. [5 ]
Boeswirth, B. [5 ]
Hunger, K. [5 ]
Neu, R. [5 ]
机构
[1] ENEA, Dept Fus & Nucl Safety Technol, I-00044 Frascati, Italy
[2] DTT SCarl, I-00044 Frascati, Italy
[3] Univ Roma Tor Vergata, Dept Ind Engn, I-00133 Rome, Italy
[4] Consorzio RFX, I-35127 Padua, Italy
[5] Max Planck Inst Plasma Phys, D-85748 Garching, Germany
关键词
Plasmas; Plasma temperature; Erosion; Thermal loading; Heating systems; Fatigue; Tokamak devices; Divertor; Divertor Tokamak Test (DTT); monoblocks; tungsten; MOCK-UPS; ITER; FABRICATION; PROGRESS; JET;
D O I
10.1109/TPS.2024.3404135
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 Divertor Tokamak Test (DTT) facility is a fusion device under construction in Italy. The mission of DTT is to test alternative divertor concepts under integrated physics and technological conditions that can reliably be extrapolated to DEMO. Due to the plasma core characteristics with relevant edge and scrape-off layer (SOL) parameters and a wall entirely in tungsten (W), DTT will provide an extensive set of information useful to select the most appropriate strategy for the power exhaust in DEMO. Several divertors, which may differ in design or/and technologies or/and poloidal profile, will be tested during the life of the machine. The first divertor to be installed will have to accommodate a multitude of strike points, located at various positions according to the different magnetic configurations, which will be tested in the first operational phases of the machine with the aim to identify the most promising. The first divertor will not test innovative technological solutions but will mainly take advantage of the technologies already qualified for the ITER divertor production. Thus, the entire divertor plasma-facing surface is designed to be used as targets: it will be made of W monoblocks joined on CuCrZr pipes (plasma-facing units, PFUs) similar to the ITER targets. With the purpose to increase the flexibility in operational scenarios by maximizing the allowable thermal load for the PFUs, the possibility of using monoblocks with a plasma side reduced thickness was investigated. By reducing the thickness of the armor, it is possible to limit plastic deformation of the monoblock and to preserve the characteristics of the plasma-facing surface during the component lifetime. A thickness between 3 and 4 mm is compatible both the erosion estimates in the DTT divertor area and the manufacturing constraints and therefore proposed for the DTT PFUs. Several mock-ups based on monoblock design were in the past tested under thermal fatigue, confirming the reliability of the monoblock design and the manufacturing processes, but with larger armor thicknesses (6-8 mm). The experimental verification of the monoblock performance with the proposed reduced thickness has been verified in the GLADIS facility at IPP Garching with a thermal load of 20 MW/m(2) applied for 1000 cycles of 10 s. The results showed the absence of plastic deformation and negligible increase in surface roughness.
引用
收藏
页码:4167 / 4173
页数:7
相关论文
共 50 条
  • [41] Self-consistent modelling of a liquid metal box-type divertor with application to the divertor tokamak test facility: Li versus Sn
    Nallo, G. F.
    Mazzitelli, G.
    Savoldi, L.
    Subba, F.
    Zanino, R.
    NUCLEAR FUSION, 2019, 59 (06)
  • [42] Study of ion cyclotron heating scenarios and fast particles generation in the divertor tokamak test facility
    Cardinali, A.
    Bolzonella, T.
    Castaldo, C.
    Ceccuzzi, S.
    Granucci, G.
    Revere, G. L.
    Tuccillo, A. A.
    Vallar, M.
    Vincenzi, P.
    PLASMA PHYSICS AND CONTROLLED FUSION, 2020, 62 (04)
  • [43] Thermal-hydraulic analysis for first wall and thermal shield of Divertor Tokamak test facility
    Maviglia, Fabio
    De Luca, Riccardo
    Roccella, Selanna
    Maddaluno, Giorgio
    Ramogida, Giuseppe
    Visca, Eliseo
    FUSION ENGINEERING AND DESIGN, 2019, 146 : 2222 - 2226
  • [44] THE DESIGN OF THE POLOIDAL DIVERTOR EXPERIMENT TOKAMAK WALL ARMOR AND INNER LIMITER SYSTEM
    KUGEL, HW
    ULRICKSON, M
    NUCLEAR TECHNOLOGY-FUSION, 1982, 2 (04): : 712 - 722
  • [45] Transient Electrical Behavior of the TF Superconducting Coils of Divertor Tokamak Test Facility During a Fast Discharge
    Messina, Giuseppe
    Lopes, Carmelo Riccardo
    Zito, Pietro
    Di Zenobio, Aldo
    Zignani, Chiarasole Fiamozzi
    Lampasi, Alessandro
    Morici, Luigi
    Ramogida, Giuseppe
    Tomassetti, Giordano
    Ala, Guido
    Zizzo, Gaetano
    IEEE TRANSACTIONS ON APPLIED SUPERCONDUCTIVITY, 2022, 32 (07)
  • [46] Status of Internal-Tin Nb3Sn Strand for Divertor Tokamak Test Facility
    Liu, Jianwei
    Shi, Yigong
    Wu, Bo
    Zhang, Ke
    Liu, Sheng
    Li, Jianfeng
    Liu, Xianghong
    Feng, Yong
    Zhang, Pingxiang
    IEEE TRANSACTIONS ON APPLIED SUPERCONDUCTIVITY, 2020, 30 (04)
  • [47] Diagnostics, data acquisition and control of the divertor test tokamak experiment
    Albanese, R.
    Ambrosino, R.
    Ariola, M.
    De Tommasi, G.
    Pironti, A.
    Cavinato, M.
    Neto, A.
    Piccolo, F.
    Sartori, F.
    Ranz, R.
    Carraro, L.
    Canton, A.
    Cavazzana, R.
    Fassina, A.
    Franz, P.
    Innocente, P.
    Luchetta, A.
    Manduchi, G.
    Marrelli, L.
    Martines, E.
    Peruzzo, S.
    Puiatti, M. E.
    Scarin, P.
    Spizzo, G.
    Spolaore, M.
    Valisa, M.
    Gorini, G.
    Nocente, M.
    Sozzi, C.
    Apicella, M. L.
    Gabellieri, L.
    Maddaluno, G.
    Ramogida, G.
    FUSION ENGINEERING AND DESIGN, 2017, 122 : 365 - 374
  • [48] THICKNESS OF THE SCRAPE-OFF LAYER OF A LARGE TOKAMAK WITH A POLOIDAL DIVERTOR
    HARBOUR, PJ
    NUCLEAR FUSION, 1984, 24 (09) : 1211 - 1215
  • [49] Design of ITER divertor VUV spectrometer and prototype test at KSTAR tokamak
    Seon, Changrae
    Hong, Joohwan
    Song, Inwoo
    Jang, Juhyeok
    Lee, Hyeonyong
    An, Younghwa
    Kim, Bosung
    Jeon, Taemin
    Park, Jaesun
    Choe, Wonho
    Lee, Hyeongon
    Pak, Sunil
    Cheon, MunSeong
    Choi, Jihyeon
    Kim, Hyeonseok
    Biel, Wolfgang
    Bernascolle, Philippe
    Barnsley, Robin
    O'Mullane, Martin
    EUROPEAN PHYSICAL JOURNAL D, 2017, 71 (12):
  • [50] Development of the electron cyclotron resonance heating system for Divertor Tokamak Test
    Garavaglia, Saul
    Balbinot, Luca
    Bruschi, Alessandro
    Busi, Daniele
    Bussolan, Andrea
    Fanale, Francesco
    Granucci, Gustavo
    Moro, Alessandro
    Platania, Paola
    Rispoli, Natale
    Romano, Afra
    Sartori, Emanuele
    Schmuck, Stefan
    Simonetto, Alessandro
    Vassallo, Espedito
    JOURNAL OF VACUUM SCIENCE & TECHNOLOGY B, 2023, 41 (04):