Surface heat loads on the ITER divertor vertical targets

被引:162
|
作者
Gunn, J. P. [1 ]
Carpentier-Chouchana, S. [2 ]
Escourbiac, F. [3 ]
Hirai, T. [3 ]
Panayotis, S. [3 ]
Pitts, R. A. [3 ]
Corre, Y. [1 ]
Dejarnac, R. [4 ]
Firdaouss, M. [1 ]
Kocan, M. [3 ]
Komm, M. [4 ]
Kukushkin, A. [5 ,6 ]
Languille, P. [1 ]
Missirlian, M. [1 ]
Zhao, W. [7 ]
Zhong, G. [7 ]
机构
[1] CEA, IRFM, F-13108 St Paul Les Durance, France
[2] EIRL S Carpentier Chouchana, F-13650 Meyrargues, France
[3] ITER Org, Route Vinon sur Verdon,CS 90 046, F-13067 St Paul Les Durance, France
[4] AS CR, Vvi, Inst Plasma Phys, Prague, Czech Republic
[5] NRC, Kurchatov Inst, Moscow 123182, Russia
[6] Natl Res Nucl Univ MEPhI, Moscow 115409, Russia
[7] Southwestern Inst Phys, POB 432, Chengdu 610041, Sichuan, Peoples R China
关键词
ITER; divertor; ELM heat load; inter-ELM heat load; tungsten; TUNGSTEN; TRANSIENT; DEPOSITION; BEHAVIOR; PARTICLE;
D O I
10.1088/1741-4326/aa5e2a
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 heating of tungsten monoblocks at the ITER divertor vertical targets is calculated using the heat flux predicted by three-dimensional ion orbit modelling. The monoblocks are beveled to a depth of 0.5 mm in the toroidal direction to provide magnetic shadowing of the poloidal leading edges within the range of specified assembly tolerances, but this increases the magnetic field incidence angle resulting in a reduction of toroidal wetted fraction and concentration of the local heat flux to the unshadowed surfaces. This shaping solution successfully protects the leading edges from inter-ELM heat loads, but at the expense of (1) temperatures on the main loaded surface that could exceed the tungsten recrystallization temperature in the nominal partially detached regime, and (2) melting and loss of margin against critical heat flux during transient loss of detachment control. During ELMs, the risk of monoblock edge melting is found to be greater than the risk of full surface melting on the plasma-wetted zone. Full surface and edge melting will be triggered by uncontrolled ELMs in the burning plasma phase of ITER operation if current models of the likely ELM ion impact energies at the divertor targets are correct. During uncontrolled ELMs in pre-nuclear deuterium or helium plasmas at half the nominal plasma current and magnetic field, full surface melting should be avoided, but edge melting is predicted.
引用
收藏
页数:35
相关论文
共 50 条
  • [31] Numerical Analysis of Fatigue Behavior of ITER-Like Monoblock Divertor Interlayer Under Coupled Heat Loads
    Huang, Shenghong
    Liu, Shimin
    JOURNAL OF FUSION ENERGY, 2018, 37 (04) : 177 - 186
  • [32] Disruption heat loads on the JET MkIIGB divertor
    Riccardo, V
    Andrew, P
    Ingesson, LC
    Maddaluno, G
    PLASMA PHYSICS AND CONTROLLED FUSION, 2002, 44 (06) : 905 - 929
  • [33] ELM induced divertor heat loads on TCV
    Marki, J.
    Pitts, R. A.
    Horacek, J.
    Tskhakaya, D.
    JOURNAL OF NUCLEAR MATERIALS, 2009, 390-91 : 801 - 805
  • [34] Overview on stationary and transient divertor heat loads
    Herrmann, A
    PLASMA PHYSICS AND CONTROLLED FUSION, 2002, 44 (06) : 883 - 903
  • [35] Modeling of Surface Composition Dynamics in the ITER Divertor Region
    Nieto-Perez, Martin
    Ramos, G.
    Allain, Jean Paul
    IEEE TRANSACTIONS ON PLASMA SCIENCE, 2010, 38 (03) : 414 - 418
  • [36] Assessment of erosion of the ITER divertor targets during type I ELMs
    Federici, G
    Loarte, A
    Strohmayer, G
    PLASMA PHYSICS AND CONTROLLED FUSION, 2003, 45 (09) : 1523 - 1547
  • [37] Results and analysis of high heat flux tests on a full-scale vertical target prototype of ITER divertor
    Missirlian, M
    Escourbiac, F
    Merola, M
    Bobin-Vastra, I
    Schlosser, J
    Durocher, A
    FUSION ENGINEERING AND DESIGN, 2005, 75-79 : 435 - 440
  • [38] Simulation of ITER transient heat loads to the divertor surfaces with using the powerful quasi-steady-state plasma accelerator
    Tereshin, V. I.
    Bandura, A. N.
    Byrka, O. V.
    Chebotarev, V. V.
    Carkusha, I. E.
    Makhlaj, V. A.
    Solyakov, D. G.
    Tsarenko, A. V.
    Landman, I.
    CZECHOSLOVAK JOURNAL OF PHYSICS, 2006, 56 : B162 - B169
  • [39] Application of powerful quasi-steady-state plasma accelerators for simulation of ITER transient heat loads on divertor surfaces
    Tereshin, V. I.
    Bandura, A. N.
    Byrka, O. V.
    Chebotarev, V. V.
    Garkusha, I. E.
    Landman, I.
    Makhlaj, V. A.
    Neklyudov, I. M.
    Solyakov, D. G.
    Tsarenko, A. V.
    PLASMA PHYSICS AND CONTROLLED FUSION, 2007, 49 (5A) : A231 - A239
  • [40] A comparative study of the effects of liquid lithium and tin as DEMO divertor targets on the heat loads and SOL properties
    Ridolfini, V. Pericoli
    Ambrosino, R.
    Mastrostefano, S.
    Chmielewski, P.
    Poradzinski, M.
    Zagorski, R.
    PHYSICS OF PLASMAS, 2019, 26 (01)