共查询到17条相似文献,搜索用时 78 毫秒
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用压缩空气炮做冲击加载装置研究一种钨合金的层裂特性,加载应力峰值为5~10 GPa,加载应力时间宽度为0.2~0.6 μs。实验用钨合金由粉末热压烧结制成,是一种均匀混合材料。它的成份重量百分比为W(90%)、Ni(6.8%)、Fe(2.7%)和Cr(0.5%)。由锰铜压阻计测量样品靶后界面应力历史表明,此种钨合金的层裂强度与拉伸应力率的平方根呈单调递增关系,与加载应力峰值无关。回收样品的金相分析结果表明,此钨合金的拉伸断裂主要发生在铁镍混合物部位,钨晶粒的穿晶断裂只占很小部分。断口上的“杯状”凹坑表明,它主要属延性断裂机制。 相似文献
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金属材料广泛应用于国防工业和民用工程中,了解金属材料在强动载荷作用下的力学性能对武器和防护结构的设计和评估具有重要意义。通过在二级轻气炮上进行平板撞击实验,测定了93钨合金和921A钢在极高应变率下的动态屈服强度,详细介绍了实验的设计原理和实验数据的分析方法,并利用公式对93钨合金和921A钢的动态屈服强度进行分析。实验结果表明:93钨合金在应变率(冲击压力)分别为1.7×105 s^?1(49.5 GPa)和3.1×105 s^?1(84.1 GPa)下的屈服强度分别为2.10 GPa和2.78 GPa;921A钢在应变率(冲击压力)为3.6×105 s^?1(38.1 GPa)、4.7×105 s^?1(62.4 GPa)和6.2×105 s^?1(90.1 GPa)下的屈服强度分别为2.08、2.67和3.15 GPa;在极高应变率下93钨合金和921A钢的动态增强因子为2~3。 相似文献
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利用两面顶压机和六面顶压机作为压力装置,分别对93钨合金材料进行了高压超声测量。测得了93钨合金材料在常态下的横、纵波声速及在0~3 GPa压力范围内的纵波声速随压力的变化关系。测量结果为:在常温常压下,93钨合金的纵波声速为cL=5.135 km/s,横波声速为ct=2.987 km/s。纵波声速随压力变化的关系式为:cL=5.053+0.602p(GPa)。估算的93钨合金相关力学参量为:G=157.4 GPa,E=393.0 GPa,K=260.2 GPa,λ=155.3 GPa,μ=157.4 GPa,ν=0.248。经过对两种超声测量方法测量结果的比较及冲击波测量数据的验证,这些参数是可靠的。 相似文献
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采用VISAR和X光联合测试技术,利用等厚对称和逆向碰撞法测量了FeMnNi合金高压加卸载历程和相变层裂信息。加载过程中,FeMnNi合金样品发生α→ε相转变,相变波速大于塑性波速,在撞击面上相变波与塑性波合并成单一相变波;卸载过程中,FeMnNi合金样品可能发生了逆相变,形成了除合并相变波在自由面反射中心稀疏波R以外的两道卸载波S1和S2。等厚对称高压加载下,FeMnNi合金样品发生了二次层裂。分析中心稀疏波R、卸载波S1和S2在样品中的传播作用过程,发现样品发生冲击相变和卸载逆转变是导致其等厚对称高压加载下发生二次层裂行为的主要原因。 相似文献
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利用正向加载和逆向加载相结合的实验方法,实验研究了从低压到高压三种不同压力范围内Fe基α相合金(Fe-85.03wt%,Mn-7.63wt%,Ni-7.01wt%,Al-0.3wt%)的冲击相变和卸载逆相变历程及对应加载状态的层裂行为特征.给出了Fe基α相合金含冲击相变和卸载逆相变的加卸载Hugoniot线,发现冲击相变阈值、逆相变阈值和冲击加载压力共同决定其冲击加卸载历程,冲击相变强烈影响其层裂行为,导致样品发生了"异常"层裂.利用获得的冲击加卸载历程从应力波相互作用的角度解
关键词:
α相合金')" href="#">Fe基α相合金
相变
逆相变
层裂 相似文献
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采用理论计算与动高压实验相结合的方法,提出了一个计算剪切模量温度系数G′T的新方法.首先用理论方法计算一个中间数据G(PS),然后再与动高压实验数据G(PH)结合在一起计算出G′T,并针对93钨合金材料进行了计算.计算结果表明剪切模量温度系数G′T开始是随温度和压力变化的,但在高温高压下,它趋近于一常数.对于93钨合金,这个常数约为-004GPa/℃.同时,这也是对Steinberg本构模型中的剪切模量温度系数为常数的一个证明.并且,当把这一常数代入剪切模量温度系数的计算式中,将重新计算出的剪切模量与实验测得的剪切模量结果进行了比较,结果表明二者符合得很好,从而证明了本计算的剪切模量温度系数的正确性.
关键词:
有限应变物态方程
剪切模量温度系数
Steinberg本构模型
动高压实验 相似文献
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用组合飞片技术以实现对待测材料93W合金进行加载-再加载和加载-卸载,并用VISAR(Velocity Interferometer System for Any Reflector)测试方法和高速数值示波器记录样品-窗口界面的粒子速度,通过上下屈服面法对实验数据进行处理,从而推出93W在冲击压力分别为16、32和96 GPa三个压力点下的屈服强度为:1.8、2.6和4.9 GPa。得到了93W合金在高压下材料屈服强度随冲击压力的增大而增大,但其与冲击压力的比值则随冲击压力的增加而减小的变化规律。 相似文献
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LaserRapidMeltingStructureandPropertyforNi-basedTungstenCarbideAlloy¥ZHANGSong;KANGYuping;SONGHuan,ZHUJingpu(ShenyangPolytech... 相似文献
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The purpose of this study was to develop a new nanocrystalline alloy material, which can replace lead for the purposes of radiation shielding as it is not hazardous to the human body and it is light in weight, to use the developed alloy in a fiber, and to evaluate its performance. This study used tungsten carbide and cobalt as the base metals and developed a new nanocrystalline alloy material. Then, radiation-shielding fibers 0.2 and 0.4?mm thick were created from the prepared tungsten carbide and cobalt powder. Equivalent dose was measured and shielding rate was obtained by the lead-equivalent test method for X-ray protection of goods suggested in the Korean Standard. According to our results, the shielding rate of the 0.2-mm-thick WC–Co alloy was 96.52% at a tube voltage of 50?kVp, 94.86% at a tube voltage of 80?kVp, and 94.10% at a tube voltage of 100?kVp. The shielding rate of the 0.4-mm-thick WC–Co alloy was 97.47% at a tube voltage of 50?kVp, 96.57% at a tube voltage of 80?kVp, and 95.63% at a tube voltage of 100?kVp. It is believed that the nanocrystalline WC–Co alloy developed for radiation shielding in this study will contribute to a decrease in primary X-ray exposure as well as exposure to low-dose secondary X-rays, such as scattered rays. Furthermore, the use of a nanocrystalline WC–Co alloy oxide rather than lead will allow for the development of shielding wear that is lighter and contribute to the development of various radiation-shielding products made of environmentally friendly materials. 相似文献
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Microstructure and hardening effect of pure tungsten and ZrO2 strengthened tungsten under carbon ion irradiation at 700℃ 下载免费PDF全文
Chun-Yang Luo 《中国物理 B》2022,31(9):96102-096102
Microstructure evolution and hardening effect of pure tungsten and W-1.5%ZrO2 alloy under carbon ion irradiation are investigated by using transmission electron microscopy and nano-indentation. Carbon ion irradiation is performed at 700 ℃ with irradiation damages ranging from 0.25 dpa to 2.0 dpa. The results show that the irradiation defect clusters are mainly in the form of dislocation loop. The size and density of dislocation loops increase with irradiation damages intensifying. The W-1.5%ZrO2 alloy has a smaller dislocation loop size than that of pure tungsten. It is proposed that the phase boundaries have the ability to absorb and annihilate defects and the addition of ZrO2 phase improves the sink strength for irradiation defects. It is confirmed that the W-1.5%ZrO2 alloy shows a smaller change in hardness than the pure tungsten after being irradiated. From the above results, we conclude that the addition of ZrO2 into tungsten can significantly reduce the accumulation of irradiated defects and improve the irradiation resistance behaviors of the tungsten materials. 相似文献
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