Modeling and simulation of melt-layer erosion during a plasma disruption

被引:30
作者
Hassanein, A
Belan, V
Konkashbaev, I
Nikandrov, L
Safronov, V
Zhitlukhin, A
Litunovsky, V
机构
[1] TROITSK INST INNOVAT & FUS RES,TROITSK,RUSSIA
[2] EFREMOV SCI RES INST,ST PETERSBURG,RUSSIA
关键词
plasma-wall interaction simulator; energy deposition; plasma disruptions; erosion and particle deposition; vaporization and melting;
D O I
10.1016/S0022-3115(97)80051-7
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Metallic plasma-facing components (PFCs) e.g. beryllium and tungsten, will be subjected to severe melting during plasma instabilities such as disruptions, edge-localized modes and high power excursions. Because of the greater thickness of the resulting melt layers relative to that of the surface vaporization, the potential loss of the developing melt-layer can significantly shorten PFC lifetime, severely contaminate the plasma and potentially prevent successful operation of the tokamak reactor. Mechanisms responsible for melt-layer loss during plasma instabilities are being modeled and evaluated. Of particular importance are hydrodynamic instabilities developed in the liquid layer due to various forces such as those from magnetic fields, plasma impact momentum, vapor recoil and surface tension. Another mechanism found to contribute to melt-layer splashing loss is volume bubble boiling, which can result from overheating of the liquid layer. To benchmark these models, several new experiments were designed and performed in different laboratory devices for this work; the results are examined and compared. Theoretical predictions (A*THERMAL-S and SPLASH codes) are generally in good agreement with the experimental results. The effect of in-reactor disruption conditions, which do not exist in simulation experiments, on melt-layer erosion is discussed.
引用
收藏
页码:288 / 293
页数:6
相关论文
共 15 条
[1]   Composition of the plasma facing material Tokamakium [J].
Behrisch, R ;
Mayer, M ;
GarciaRosales, C .
JOURNAL OF NUCLEAR MATERIALS, 1996, 233 :673-680
[2]   Features of dynamics and structure of the shielding layer at the interaction of plasma flow with target [J].
Belan, VG ;
Levashov, VF ;
Maynashev, VS ;
Muzichenko, AD ;
Podkovirov, VL .
JOURNAL OF NUCLEAR MATERIALS, 1996, 233 :763-766
[3]   On a possibility of explosive material erosion under conditions of ITER disruption event [J].
Burdakov, AV ;
Chagin, MN ;
Filippov, VV ;
Koidan, VS ;
Mekler, KI ;
Melnikov, PI ;
Postupaev, VV ;
Rovenskikh, AF ;
Shcheglov, MA ;
Tsigutkin, KV ;
Wuerz, H .
JOURNAL OF NUCLEAR MATERIALS, 1996, 233 (Pt A) :697-700
[4]  
BURTSEVA T, 1995, PLASMA DEVICES OPER, V4, P31
[5]   MECHANISMS RESPONSIBLE FOR TOPOGRAPHICAL CHANGES IN PLT STAINLESS-STEEL AND GRAPHITE LIMITERS [J].
COHEN, SA ;
BUDNY, R ;
MCCRACKEN, GM ;
ULRICKSON, M .
NUCLEAR FUSION, 1981, 21 (02) :233-249
[6]   VAPOR SHIELD PROTECTION OF PLASMA FACING COMPONENTS UNDER INCIDENT HIGH HEAT-FLUX [J].
GILLIGAN, J ;
BOURHAM, M ;
HANKINS, O ;
EDDY, W ;
HURLEY, J ;
BLACK, D .
JOURNAL OF NUCLEAR MATERIALS, 1992, 196 :596-601
[7]   Lifetime evaluation of plasma-facing materials during a tokamak disruption [J].
Hassanein, A ;
Konkashbaev, I .
JOURNAL OF NUCLEAR MATERIALS, 1996, 233 (Pt A) :713-717
[8]  
HASSANEIN A, 1994, NUCL FUSION, V5, P193
[9]   PLASMA DISRUPTION MODELING AND SIMULATION [J].
HASSANEIN, A .
FUSION TECHNOLOGY, 1994, 26 (03) :532-539
[10]  
HASSANEIN A, 1996, ANLFPPTM286