MODELS AND SIMULATION FOR DIVERTOR EROSION FOLLOWING PLASMA DISRUPTION IN TOKOMAK REACTORS

被引:0
|
作者
Almousa, N. M. [1 ]
Gilligan, J. G. [1 ]
Bourham, M. A. [1 ]
机构
[1] North Carolina State Univ, Dept Nucl Engn, Raleigh, NC 27695 USA
关键词
Tokamak disruption; plasma facing components; surface erosion; vapor and melt layer shielding; TOKAMAK DISRUPTION; FACING COMPONENTS; ITER DIVERTOR; GUN;
D O I
暂无
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
Erosion of plasma facing materials (PFMs) during a tokamak disruption limits the lifetime and increases the need of plasma facing components (PFCs) replacement in the reactor. During disruption, energetic plasma particles deposit high heat fluxes on the PFCs. It has been shown theoretically and experimentally that the deposited energy by plasma particles vaporizes the surface of the PFMs. Besides vaporization some selected metallic PFMs, such as tungsten and molybdenum, may suffer severe surface erosion due to melting. Melting and vaporization of metallic PFMs develop a boundary layer adjacent to the PFCs which shields such critical components as vapor shield, melt-layer shield or mixed melting/vapor shield. Part of the incoming heat flux is being absorbed by the dense and optically thick boundary layer evolved from the exposed surface, which significantly decreases the erosion of the PFCs. The accurate calculations of the net heat flux that hits the surface of PFCs during disruption are of great importance. In this study, the erosion of metallic PFMs is governed by vapor and droplet formation and their associated shielding effects. Fully self consistent erosion models are developed and implemented in the ETFLOW code in a new version (ETFLOW-BL) to model the PFMs response as they experience such disruption conditions. The melt -layer and vaporization losses following a disruption are calculated in this study for different values of incident plasma energies relevant to those expected in ITER. The calculated initial sharp rise in the PFMs erosion is due to the direct energy deposition on the PFCs surfaces. As disruption time goes on, boundary layers will accumulate adjacent to PFC surface and less energy penetrates to the original surface, which results in less boiling, scattering and vaporization. Comparisons between cases where both vaporization and melting process takes place are presented. Corresponding mass losses, and erosion thickness, are estimated for both cases.
引用
收藏
页数:5
相关论文
共 50 条
  • [21] NUMERICAL MODELING AND EXPERIMENTAL SIMULATION OF VAPOR SHIELD FORMATION AND DIVERTOR MATERIAL EROSION FOR ITER TYPICAL PLASMA DISRUPTIONS
    WURZ, H
    ARKHIPOV, NI
    BAKHIN, VP
    GOEL, B
    HOBEL, W
    KONKASHBAEV, I
    LANDMAN, I
    PIAZZA, G
    SAFRONOV, VM
    SHERBAKOV, AR
    TOPORKOV, DA
    ZHITLUKHIN, AM
    JOURNAL OF NUCLEAR MATERIALS, 1994, 212 (pt B) : 1349 - 1352
  • [22] Erosion and deuterium retention investigation of mixed W-Be layers on Be in experiments on plasma disruption simulation
    Korshunov, SN
    Vasiliev, VI
    Guseva, MI
    Gureev, VM
    Danelyan, LS
    Zatekin, VV
    Kulikauskas, VS
    FUSION TECHNOLOGY, 2000, 38 (03): : 357 - 362
  • [23] SELFSPUTTERING OF BERYLLIUM AND SPUTTERING AND EROSION OF C-C COMPOSITE IN THE EXPERIMENTS ON PLASMA DISRUPTION SIMULATION
    GUSEVA, MI
    GUREEV, VM
    KORSHUNOV, SN
    NEUMOIN, VE
    SOKOLOV, YA
    STOLYAROVA, VG
    VASILIEV, VI
    RYLOV, SV
    STRUNNIKOV, VM
    JOURNAL OF NUCLEAR MATERIALS, 1995, 220 : 957 - 960
  • [24] Erosion and deuterium retention investigation of mixed W-Be layer on Be in experiments on plasma disruption simulation
    Korshunov, SN
    Vasiliev, VI
    Guseva, MI
    Gureev, VM
    Danelyan, LS
    Zatekin, VV
    Kulikauskas, VS
    PROCEEDINGS OF THE 4TH IEA INTERNATIONAL WORKSHOP ON BERYLLIUM TECHNOLOGY FOR FUSION, 2000, 6462 : 285 - 290
  • [25] EROSION AND MICROSTRUCTURE CHANGE OF MATERIALS DURING DISRUPTION-SIMULATION EXPERIMENTS IN PLASMA-ACCELERATOR
    KALIN, BA
    POLSKY, VI
    YAKUSHIN, VL
    VIRGILEV, YS
    VASILIEV, VI
    TSEREVITINOV, SS
    JOURNAL OF NUCLEAR MATERIALS, 1995, 220 : 934 - 938
  • [26] PLASMA DISRUPTION MODELING AND SIMULATION
    HASSANEIN, A
    FUSION TECHNOLOGY, 1994, 26 (03): : 532 - 539
  • [27] Plasma disruption modeling and simulation
    Hassanein, A.
    Fusion Technology, 1994, 26 (3 pt 2): : 532 - 539
  • [28] Disruption simulation for the EAST plasma
    Niu, Xing-Ping
    Wu, Bin
    Hejubian Yu Dengliziti Wuli/Nuclear Fusion and Plasma Physics, 2007, 27 (04): : 286 - 291
  • [29] Divertor conditions relevant for fusion reactors achieved with linear plasma generator
    van Eck, H. J. N.
    Kleyn, A. W.
    Lof, A.
    van der Meiden, H. J.
    van Rooij, G. J.
    Scholten, J.
    van Emmichoven, P. A. Zeijlmans
    APPLIED PHYSICS LETTERS, 2012, 101 (22)
  • [30] Surface erosion of tungsten and the morphology of erosion products in experiments simulating plasma disruption
    Guseva, MI
    Gureev, VM
    Domantovskii, AG
    Martynenko, YV
    Moskovkin, PG
    Stolyarova, VG
    Strunnikov, VM
    Plyashkevich, LN
    Vasil'ev, VI
    TECHNICAL PHYSICS, 2002, 47 (07) : 841 - 844