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首页> 外文期刊>Journal of Nuclear Materials: Materials Aspects of Fission and Fusion >EXAMINATION OF MATERIAL PERFORMANCE OF W EXPOSED TO HIGH HEAT LOAD - POSTMORTEM ANALYSIS OF W EXPOSED TO TEXTOR PLASMA AND E-BEAM TEST STAND
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EXAMINATION OF MATERIAL PERFORMANCE OF W EXPOSED TO HIGH HEAT LOAD - POSTMORTEM ANALYSIS OF W EXPOSED TO TEXTOR PLASMA AND E-BEAM TEST STAND

机译:高热负荷下钨的材料性能检验-纺织等离子体和电子束测试台的钨的物相分析。

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We have examined the behavior of high Z limiters exposed to TEXTOR edge plasma and found that under certain conditions high Z materials are compatible with plasmas. In high density Ohmic plasmas the accumulation of a high Z impurity in the plasma center with significant radiation is observed, whereas an auxiliary heating like NBI and ICRH enhances the impurity exhaust with saw tooth activity. For a practical use of high Z plasma facing materials, extremely high heat load from the plasma becomes a serious concern. In the present work we have conducted the high heat load tests of tungsten (W) using two different heat sources, one is the W limiter exposed to TEXTOR plasma and tile other is various W samples heat loaded with an intense E-beam using the JEBIS facility in Japan Atomic Energy Research Institute (JAERI). From the test results we have to conclude that W, if applied in the form of the bulk material, should be used above the ductile brittle transition temperature (DBTT) but below about 1500 degrees C to avoid the recrystallization. Maximum heat load tolerable without surface melting is about 20 MW/m(2) for several seconds, The monocrystalline used at high temperatures shows very good performance, though the production of the monocrystalline with a desired shape is not easy, Considering its brittle nature, hard machining and heavy mass, bulk W cannot be a structure material but be used as a thin tile or deposited film on some structure materials. Unfortunately, however, the thermal expansion coefficient of W is so small that brazing of W to a heat sink material like Cu which has a much larger thermal expansion coefficient would easily result in cracking due to the large thermal stress. Thus the development of tungsten plasma facing component (PFC) needs much effort in future. [References: 11]
机译:我们检查了暴露于TEXTOR边缘等离子体的高Z限幅剂的行为,发现在某些条件下高Z材料与等离子体兼容。在高密度欧姆等离子体中,观察到高Z杂质在具有明显辐射的等离子体中心的聚集,而辅助加热(如NBI和ICRH)则增强了锯齿活动的杂质排放。对于高Z等离子体面对材料的实际使用,来自等离子体的极高的热负荷成为严重的问题。在当前的工作中,我们使用两种不同的热源对钨(W)进行了高热负荷测试,一种是暴露于TEXTOR等离子体和瓷砖上的W限幅器,另一种是使用JEBIS对各种W样品进行了强力电子束热负荷日本原子能研究所(JAERI)的工厂。根据测试结果,我们必须得出结论,如果W以散装材料的形式施加,则应在高于韧性脆性转变温度(DBTT)但低于1500摄氏度的温度下使用,以避免重结晶。在几秒钟内无表面熔化的情况下,可承受的最大热负荷约为20 MW / m(2)。在高温下使用的单晶硅具有非常好的性能,尽管要制造具有所需形状的单晶硅并不容易,考虑到其脆性,坚硬的机械加工和沉重的质量,块体W不能用作结构材料,而可以用作薄砖或某些结构材料上的沉积膜。然而,不幸的是,W的热膨胀系数太小,以致于将W钎焊到具有大得多的热膨胀系数的诸如Cu的散热材料上,由于大的热应力而容易导致破裂。因此,钨等离子面对部件(PFC)的开发在将来需要付出很大的努力。 [参考:11]

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