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 共查询到19条相似文献,搜索用时 360 毫秒
1.
ODS铁素体合金抗辐照损伤性能   总被引:1,自引:0,他引:1  
利用电子辐照、离子辐照等多种辐照模拟方法,对机械合金化方法制备的氧化物弥散强化铁素体合金抗辐照损伤性能进行了研究.实验表明:在抗辐照肿胀和抗辐照偏析方面,所研制的材料明显优于对照实验的奥氏体合金;积分通量1.7×1017/cm2氩离子注入,引起表层起泡、龟裂,劣于对照材料,辐照后初脆转变温度高于Fe—13%Cr合金,存在轧制造成的强度各向异性问题,材料韧性有待提高.  相似文献   

2.
难熔高熵合金在反应堆结构材料领域的机遇与挑战   总被引:1,自引:0,他引:1  
传统反应堆结构材料性能已趋于极限,亟需开发新型材料。难熔高熵合金是以多种难熔元素作为主元的新型金属材料,具有独特的力学、物理和化学性质,尤其在高温力学、抗辐照等方面表现出优异的性能。难熔高熵合金在第4代核裂变反应堆包壳材料、核聚变堆面向第一壁材料等关键领域具有广阔的应用前景。本文结合具有代表性的文献,围绕难熔高熵合金的力学性能、抗辐照性能、抗氧化性能阐述了其强化机制与抗辐照机理,梳理了难熔高熵合金的发展脉络,在此基础上展望了难熔高熵合金在反应堆结构材料领域的应用前景。  相似文献   

3.
锆—4合金的水蒸汽腐蚀动力学   总被引:1,自引:0,他引:1  
研究了1000℃~1300℃锆-4合金的水蒸汽腐蚀动力学。实验所用材料为锆-4合金管,实验方法为等温氧化实验方法,实验发现,锆-4合金的腐蚀动力学符合抛物线规律:(△W)^2=2.008×10^8.t.exp(-17826/T),随腐蚀反应时间的逐渐延长,锆-4合金的腐蚀反应动力学不再遵循抛物线规律,腐蚀动力学曲线向上偏离初期的抛物线,出现“加速腐蚀”现象。扫描电镜分析表明,长时间水蒸汽腐蚀后的“  相似文献   

4.
离子注入Ce对Ni20Cr合金抗氧化性能的影响   总被引:1,自引:0,他引:1  
李美栓  彭晓 《金属学报》1994,30(4):B169-B174
注入剂量为2×10^16,5×10^17/cm^2的Ce^+,使Ni20Cr合金在1000和1100℃下的氧化速率显著降低,氧化膜致密,完整,粘附性好,利用离子探针分析技术测量了注Ce^+后,合金元素在合金表面及1100℃形成的氧化膜内结合能差,注Ce^+后降低了合金表面Cr^+的结合能,有利于其向外扩散从而快速成膜;增大了膜内Cr^+ nI^+  相似文献   

5.
采用放电等离子烧结技术制备了W28Ta28V28Zr8Sc8高熵合金,研究了高熵合金在低能量、高通量氦离子辐照下的损伤行为。结果表明,在相同He离子辐照参数下,高熵合金表现出比纯W更优异的抗辐照损伤性能。不同He离子能量条件下,高熵合金中出现严重Fuzz结构时的He离子能量阈值远高于纯W。在相同辐照参数下,高熵合金有着明显小于纯W的Fuzz层厚度。W28Ta28V28Zr8Sc8高熵合金中不同相区在辐照后表现出不同的表面形貌特点,这与构成相区主要元素的He离子辐照行为有关。通过设计高熵合金的显微组织,可以获得优良的抗辐照材料。  相似文献   

6.
离子注入Ce对Fe—23Cr—5Al合金上AI2O3膜生长应力的影响   总被引:1,自引:0,他引:1  
李美栓  钱余海 《金属学报》1999,35(9):975-980
利用双面氧化弯曲方法原位测量了Fe-23Cr-5Al合金空气中氧化形成的AI2O3膜平均生长应力。AI2O3膜内存在压应力。900℃下氧化20h,膜内应力从3.5降低到2GPa,1000℃下氧化10h,膜内应力从0.8降低到0.4GPa,合金表面离子注入1×10^17Ce^+/cm^2,增大了AI2O3膜的生长应力,其原因是添加稀土促进膜的横向生长,离子注入Ce同时增大了合金的氧化速率,促进了AI  相似文献   

7.
本文采用粉末冶金技术制备了CrMn0.3FeVCu0.06高熵合金合金,并系统研究了合金的微观组织、力学性能及抗辐照性能,结果表明,采用粉末冶金制备的CrMn0.3FeVCu0.06合金由BCC结构的固溶体基体和FCC结构的第二相颗粒组成,且由于合金的晶粒尺寸和第二相颗粒的尺寸较小,晶界强化和弥散强化效应有效地提高了合金的强度和硬度,此外,由于第二相颗粒为FCC软相,颗粒起到弥散强化的同时又不会严重降低合金的塑性,因此,CrMn0.3FeVCu0.06合金同时具备高强度和优异的塑韧性。CrMn0.3FeVCu0.06合金的D等离子体辐照试验表明,在500 K、40 eV、1×1022 m-2s-1的辐照条件下,合金内部产生辐照气泡需要的临界辐照剂量Φcr大于2.0×1025 m-2,远大于同等辐照条件下在多晶钨中产生气泡的临界剂量,合金的抗辐照鼓泡性能优于传统的多晶钨,且随着辐照剂量的增大,合金表面的辐照气泡尺寸逐渐增大。此外,合金的纳米压痕测试结果表明,辐照温度和剂量对合金辐照硬化效应的作用是相反的,合金的硬度随着剂量的增大而升高,随温度的升高而降低,且由于CrMn0.3FeVCu0.06高熵合金中存在严重的晶格畸变和迟滞扩散效应,合金的辐照硬化效应对温度变化更敏感。  相似文献   

8.
添加剂对化学镀镍过程的影响   总被引:2,自引:0,他引:2  
利用循环发技术及阴、阳极极化等方法研究了化学镀镍磷合金的沉积过程及加速剂的影响。结果表明,Ni^2+的还原反应与H2PO2^-的氧化反应之间存在的着重要的相互作用即诱地共析作用;加速剂的加入,提高了H2PO2^-的氧化能力,使反应激活能降低,因而加速了化学镀镍沉积反应。  相似文献   

9.
综述了国内外广泛研究的W-La2O3和W-TiC合金的制备工艺、力学性能和辐照性能的研究进展。结果表明:向钨基体中加入La2O3弥散相,虽然能够显著改善钨的强度和韧性,但使钨的抗辐照性能降低,氢泡密度和氢滞留量明显增加;当采用TiC纳米颗粒作为弥散相,经过热等静压烧结和塑性加工后,钨合金的抗弯强度达到4.4 GPa,再结晶温度高于2 473K,韧脆转变温度(DBTT)比纯钨的低100 K;TiC的加入能够显著提高钨的抗辐照性能,与纯钨相比,氚滞留量减小,没有明显的辐照硬化,材料表面没有裂纹和剥落。  相似文献   

10.
用于核反应堆的新候选材料研发是一项重要任务。由于反应堆环境恶劣,堆芯材料在高温下应具有良好的综合性能,如良好的强度、延展性、耐腐蚀性能和耐辐照性能等。此外,还应考虑低中子吸收横截面和中子活化。典型的空间核反应堆核心材料的选择主要由工作温度决定。随着反应堆设计工作温度的升高,一般以316不锈钢、镍基高温合金、氧化物分散强化(ODS)钢、铌合金、难熔金属和SiC陶瓷的顺序来选择设计堆芯材料。此外,高熵合金已经引起核领域的广泛关注。本文综述了以上不同材料体系在辐照过程中的力学性能演变,为进一步提升抗辐照性能提供研究指导。  相似文献   

11.
Oxide-dispersion-strengthened (ODS) high-temperature alloys represent a unique class of powder-metallurgy-based engineering materials. They offer combinations of high-temperature strength, oxidation resistance, and hot corrosion resistance that cannot be obtained in other alloys. The alloys were initially developed for the aircraft gas turbine industry; since then, however, applications have expanded to include industrial gas turbines, equipment for handling molten glass, high-temperature furnace assemblies, and a variety of other industrial components. Internationally, the materials are also of interest for nuclear power systems (both breeder and fusion reactors) since ferritic ODS alloys exhibit both excellent swelling resistance and good elevated-temperature creep resistance. Many of these applications require that the ODS alloys be joined to either themselves or to other materials. The purpose of this paper is to review some of the techniques available for making these joints.  相似文献   

12.
The processes of accumulation and annealing of radiation defects at low-temperature (77 K) electron and neutron irradiation and their effect on the physicomechanical properties of Fe-Cr alloys and oxide dispersion strengthened (ODS) steel have been studied. It has been shown that the behavior of radiation defects in ODS steel and Fe-Cr alloys is qualitatively similar. Above 250 K, radiation-induced processes of the solid solution decomposition become conspicuous. These processes are much less pronounced in ODS steel because of specific features of its microstructure. Processes related to the overlapping of displacement cascades under neutron irradiation have been considered. It has been shown that, in this case, it is the increase in the size of vacancy clusters, rather than the growth of their concentration, that is prevailing. Possible mechanisms of the radiation hardening of the ODS steel and the Fe-13Cr alloy upon irradiation and subsequent annealing have been discussed.  相似文献   

13.
Several oxide dispersion strengthened (ODS) alloys have been tested for cyclic, long-term, high gas-velocity resistance to oxidation at 1100°C and hot corrosion at 900°C. Both nominally Ni-16Cr-4Al and Fe-20Cr-4.5Al ODS alloys were subjected up to 2500 cycles, where each cycle consisted of 1 hr in a hot, Mach 0.3 combusted gas stream followed by a 3-min quench in an ambient temperature, Mach 0.3 air blast. For comparison to existing technology, a coated superalloy was simultaneously tested. The ODS iron alloy exhibited clearly superior behavior, surviving 3800 oxidation and 2300 hot corrosion cycles essentially unscathed. While the ODS nickel alloys exhibited adequate oxidation resistance, the long-term hot corrosion resistance could be marginal, since the best life for such alloys under these conditions was only 1100 cycles. However, the hot corrosion resistance of the ODS Ni-base alloys is excellent in comparison to that of traditional superalloys.  相似文献   

14.
Effect of friction stir welding (FSW) on microstructure and creep properties of oxide dispersion strengthened (ODS) alloy MA754 were investigated. Fine-grained microstructure developed in the weld zone. TEM results showed some degree of particle agglomeration as a result of intense material flow. Creep tests of the FSW material were carried out at 973 and 1073 K. Power law creep behaviour was observed with stress exponent values of 6.9 and 6.3 at 973 and 1073 K, respectively. The results were compared to those of the as-received material. Creep resistance of FSW material was lower than that of as-received material associated with significantly reduced threshold stress. Post-weld annealing was carried out at 1598 K for 1 h. The heat treatment resulted in a coarse-grained microstructure and enhanced the creep resistance of the welded material. The creep data were compared with those of ODS Ni-Cr alloys in literature. The analysis shows the threshold stress of ODS alloys to be grain size- and temperature-dependent.  相似文献   

15.
Chromium based ODS alloys are being discussed as interconnector materials in solid oxide fuel cells (SOFC's). One of the major requirements for the interconnect material is sufficient corrosion resistance in the anode and cathode side gases at the operating temperature of around 950°C. In the present study the corrosion behaviour of a number of chromium based ODS alloys has been investigated in carbon containing simulated anode gas of an SOFC. Under these experimental conditions all alloys studied are prone to carburization. The carbon uptake, which mainly occurs in the early stages of exposure, leads to the formation of a mixed carbide/oxide layer beneath the external chromia scale. The carburization resistance of the alloys depends on the type and concentration of the oxide dispersion but even to a larger extent on its distribution. Therefore the careful control of the alloy manufacturing process is of great significance for obtaining sufficient carburization resistance under SOFC conditions.  相似文献   

16.
The microstructure and nano-hardness of the pure copper and oxide dispersion-strengthened(ODS) copper alloy subjected to 1.4 Me V Au ions irradiation at room temperature were investigated. After irradiation, dislocation-loops form in both materials, while voids can only be generated in the pure copper. Compared with the irradiated pure copper, larger average diameter and lower number density of irradiation-induced dislocation-loops were detected in the ODS copper alloy, revealing that high-density dislocation and large volume of Al_2O_3 particles existing in the ODS copper alloy can act as effective sinks for the irradiation-induced defects. It was also detected that irradiation hardening in the ODS copper alloy is lower than that in the pure copper. The microstructure and nano-hardness results reveal that the ODS copper alloy has a better irradiation tolerance than the pure copper. In addition, the average diameter of the Al_2O_3 particles in the ODS copper alloy decreases after irradiation, because the Al–O chemical bonds are decomposed and the atoms are redistributed in the matrix during the irradiation process. This work reveals that the irradiation tolerance of the copper can be effectively enhanced by adding nano-sized Al_2O_3 particles into the matrix.  相似文献   

17.
Four experimental oxide dispersion strengthened (ODS)Fe-(13–14 at. %)Cr ferritic alloys were exposed for up to 10,000 hr at 700–1100 °C in air and in air with 10vol.% water vapor. Their performance has been compared to other commercial ODS and stainless steel alloys. At 700–800°C, the reaction rates in air were very low for all of the ODS Fe–Cr alloys compared to stainless steels. At 900°C, a Y2O3 dispersion showed a distinct benefit in improving oxidation resistance compared to an Al2O3 dispersion or no addition in the stainless steels. However, for the Fe-13 %Cr alloy, breakaway oxidation occurred after 7,000 hr at 900°C in air. Exposures in 10 % water vapor at 800 and 900°C and in air at 1000 and 1100°C showed increased attack for this class of alloys. Because of the relatively low Cr reservoirs in these alloys, their maximum operating temperature in air will be below 900°C.  相似文献   

18.
The oxidation of six oxide dispersion strengthened (ODS) ferritic alloys was investigated at 1050 °C in air up to 200 h. Al plays the dominant role in improving the oxidation resistance of the ODS alloys. Cr and Y are of importance in forming the stable Al2O3 scale. To produce the dense alumina layer with enhanced adherence to the metal substrate, the concentrations of Al and Cr should be larger than 2 and 14 wt.%, respectively.  相似文献   

19.
NiAl based oxide dispersion strengthened (ODS) intermetallic alloys have been produced by mechanical alloying (MA) and consolidated by hot extrusion. Subsequent isothermal annealing was carried out to induce normal grain growth (NGG), and a thermomechanical treatment was performed to induced secondary recrystallization (SRx). SRx resulted in pronounced elongated grain growth without dispersoid coarsening, whereas concurrent equiaxed coarsening of grains and dispersoids occurred in NGG specimens. Creep properties of grain coarsened ODS MA NiAl were investigated, and the associated creep mechanisms were evaluated. The creep properties of SRxed MA NiAl are compared with those of as-consolidated MA NiAl and other counterparts. It has been shown that SRx results in improved creep resistance compared to NGG mechanism. The apparent activation energy and the stress exponent for creep indicate that SRx MA NiAl exhibits intermediate creep behavior of the two limiting dislocation creep modes; climb, controlled and viscous glide controlled. However, a grain size dependent creep has been shown, indicating that grain boundary sliding mechanism contributes to the overall deformation in MA NiAl.  相似文献   

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