Hydrogen permeability over the joint weld of the steel parts of fusion reactor with magnet confinement of plasma

被引:5
作者
Fedorov, VV
Dyomina, EV
Zasadny, TM
Ivanov, LI
Prusakova, MD
Vinogradova, NA
Zabelin, AM
机构
[1] RAS, Baikov Inst Met & Mat Sci, Moscow 117334, Russia
[2] Phys Mech Inst, UA-290601 Lvov, Ukraine
[3] Inst Laser & Informat Technol, Shatura 140700, Russia
关键词
Diffusion - Hydrogenation - Plasmas - Solubility - Steel - Thermal effects - Welds;
D O I
10.1016/S0022-3115(02)01289-8
中图分类号
T [工业技术];
学科分类号
08 ;
摘要
Hydrogen and its isotopes diffusion and permeability over the laser joint weld of low-activation 10Cr9WVA ferritic steels have been studied. Welding of steel sheets were produced with the help of Russian gas laser TL-5M type (l = 10.6 mm, P = 2.5 kW) in He atmosphere with the rate of 66 mm./s. Hydrogen diffusion over the joint welds was detected by the conventional method of electrical resistance measurement. By this way, the kinetics of resistance changes during hydrogenation of specimens engraved from weld metal, neighboring zone of thermal effect as well as basic metal have been determined. Coefficients of hydrogen diffusion were measured in the temperature range from 773 to 1073 K. So, for 10Cr9WVA steel at 873 K it was established that the hydrogen diffusion coefficient in the weld metal is approximately 10 times higher than in the basic metal, and three times higher than that in the zone of thermal effect. Hydrogen permeability over the joint weld specimens was measured by the Dines-Barrer method on the volummetric. setup. It was established that the hydrogen flux over the laser joint weld is significantly (up to two, orders) more than that over the basic metal. Using the data on the hydrogen permeability and diffusion coefficient, the hydrogen solubility in the weld metal was estimated, which is several ten times higher than that in the basic metal of the steel investigated. As a result, it was concluded that welding the steel parts of the first wall of thermonuclear reactors with magnet confinement of plasma is undesirable due to possible tritium leaking into the environment. A possible way of decreasing the joint welds hydrogen permeability, including application of protective impermeable for hydrogen coatings, is considered. (C) 2002 Published by Elsevier Science B.V.
引用
收藏
页码:1498 / 1501
页数:4
相关论文
共 10 条
[1]   Effect of hydrogen treatment on structure and phase state and hydrogen permeability of low-activation 10Cr12Mn20W and 10Cr9WVA steels [J].
Dyomina, EV ;
Fedorov, VV ;
Ivanov, LI ;
Zasadny, TD ;
Prusakova, MD ;
Vinogradova, NA .
FUSION ENGINEERING AND DESIGN, 2000, 51-52 (51-52) :93-98
[2]   HYDROGEN PERMEABILITY OF AUSTENITIC STEELS PROPOSED FOR FUSION-REACTOR FIRST WALL [J].
FEDOROV, VV ;
POKHMURSKY, VI ;
DYOMINA, EV ;
PRUSAKOVA, MD ;
VINOGRADOVA, NA .
FUSION TECHNOLOGY, 1995, 28 (03) :1153-1158
[3]  
FYODOROV VV, 1995, PHYS CHEM MAT TREATM, V6, P88
[4]  
FYODOROV VV, 1987, USING CONDUCTIVITY M
[5]  
KLUEH RL, 1998, DOEER031325, P111
[6]  
NIKIFOROV AS, STRUCTURE MAT FUSION, P28
[7]  
POHODNJA IK, 1980, AUTOMAT WELD, V1, P37
[8]   Diffusion and permeation of hydrogen in low-activation martensitic stainless steel - effect of irradiation [J].
Schliefer, F ;
Liu, C ;
Jung, P .
JOURNAL OF NUCLEAR MATERIALS, 2000, 283 (PART I) :540-544
[9]   Hydrogen behaviour in aged low activation martensitic steel F82H for fusion reactor applications [J].
Serra, E ;
Benamati, G .
MATERIALS SCIENCE AND TECHNOLOGY, 1998, 14 (06) :573-578
[10]  
TARLINSKY VD, 1980, AUTOMAT WELD, V11, P21