Zr-4合金低周疲劳特性研究

研究了再结晶态Zr-4合金板材在室温和400 ℃下的低周疲劳特性.Zr-4合金在室温下的循环变形行为与应变幅有关,当应变幅小于0.8%时,表现为循环软化;应变幅大于0.8%时,表现为循环硬化.在400 ℃下均表现为循环硬化.合金在室温和400 ℃下,均遵循Coffin-Manson关系.在低应变幅下,室温的低周疲劳性能明显优于400 ℃下的低周疲劳性能,随着应变幅的增加,两者寿命趋于接近.用扫描电子显微镜观察分析了合金在室温和400 ℃下的疲劳断口特征.     

Zr-4合金小试样高温疲劳行为研究

基于Zr-4合金漏斗薄片小试样,完成了室温和400℃高温下的等幅横向应变循环与应变疲劳试验.根据弹塑性有限元分析,建立了基于局部应变等效的应变换算方法,并结合实验结果,得到了估算Zr-4合金应变疲劳寿命的Manson-Coffin模型.结果表明:低应变幅下,Zr-4合金表现出循环软化特征;高应变幅下,Zr-4合金表现出循环强化特征.高温严重降低了低应变幅下Zr-4合金的疲劳寿命,随着应变幅增加,温度影响趋弱.分析表明,基于传统应变转换公式的M-C模型用于估算疲劳寿命偏于保守.     

织构对Zr-4合金循环变形行为的影响

研究了织构对Zr-4合金循环变形行为的影响及其作用机制。结果表明，(1)合金的低周疲劳寿命遵循Coffin—Manson关系N^(β)f△εpC。在给定△εp时，轧向的寿命比横向的长。随△εp的降低，两个方向的疲劳寿命差别增大；(2)在低应变幅，合金表现为循环软化直至疲劳破坏在高应变幅，循环变形的初期表现为循环硬化，随后是循环软化直至疲劳破坏在应变幅恒定时，随着循环次数的增加，晶粒发生转动，使晶粒有更高的Schmid因子；(3)半寿命时的σs随εp的变化遵循乘幂关系σs=K^sε(^n^s),σid随σp的变化则遵循对数关系σid=K^blnεp Cb；(4)轧向和横向之间循环变形行为的差别是由于织构效应的缘故。     

N18合金薄壁管高温应变循环与疲劳行为研究

应用新型自研夹具对N18合金薄壁短管进行400℃下的单轴拉伸和等幅低周应变疲劳试验。试验结果表明：N18短管高温循环应力应变滞回线有良好对称性；等幅循环下短管试样在较低应变幅下表现出循环硬化特性，而在较高应变幅下表现出循环软化；在多级应变循环加载下短管试样应力幅在循环中均保持稳定，循环本构关系不受多级应变循环工况差异的影响；材料循环特性不符合Manson律。获得了用于N18合金在400℃高温下的几个寿命估算式。     

N18锆合金的低周疲劳行为

在不同试验温度（室温～500℃）下,对N18合金进行了低周疲劳试验。试验结果表明：室温～300℃温区,合金表现为明显的循环软化;400、450℃时,合金逐渐呈现循环硬化,450℃时其硬化现象更为明显;500℃时则主要表现为循环饱和。随着温度的升高,疲劳寿命先增加后降低,300℃时疲劳寿命最高。低应变幅下,温度对疲劳寿命的影响更明显。通过疲劳断口SEM分析,室温下疲劳起源于单个裂纹源,疲劳裂纹扩展阶段的微观特征主要是疲劳条纹,局部区域出现轮胎状花样。在高温下为多裂纹源,大量二次裂纹的存在是高温疲劳断口的主要特征。     

ZIRLO合金和Zr-4合金在LiOH水溶液中耐腐蚀性能的研究

比较了ZIRLO合金和Zr-4合金两种样品在350℃、16．8MPa、0．04MLiOH水溶液中的耐腐蚀性能，发现Zr4合金样品在腐蚀转折之前的腐蚀增重比ZIRLO合金稍低，这时两种样品的氧化膜相对完整而致密。用二次离子质谱仪(SIMS)测量Li^ 在两种合金样品氧化膜剖面中的分布，发现Li^ 进入Zr-4合金氧化膜的深度比ZIRLO合金浅，但浓度比较高。而腐蚀至68天在Zr—4合金样品腐蚀发生转折后，其腐蚀增重远高于ZIRLO合金，这是因为此时Zr-4合金样品氧化膜因疏松而失去保护作用，而ZIRLO合金样品腐蚀至82天氧化膜仍致密而完整。ZIRLO合金中细小的βNb和Zr—Fe—Nb第二相粒子可能对保持氧化膜的完整性有重要作用。     

低铌新锆合金的抗蠕变性能

通过对低铌新锆合金板材的蠕变性能曲线和变形亚结构的分析及对微观组织研究探讨了低铌新锆合金的蠕变过程及其抗蠕变性能优越的原因.铌对锆有较高的强化作用,但对锆的抗蠕变性能的影响则较为复杂.含3%～5%Nb的锆合金在400 ℃以下有较高的抗蠕变性能,含15%Nb的锆合金的抗蠕变性最低,而铌含量增至30%时的锆合金的抗蠕变性则又升高.低Nb新锆合金的Nb含量w(Nb)在0.3%～0.36%之间,这样少的Nb含量不可能有大量的β-Nb相产生,它对锆合金的强化作用应归于固溶强化一类.对工业化规模生产的低铌新锆板材的力学性能的近期研究表明,按既定工艺生产的低铌新锆合金板材的拉伸性能并未比Zr-4合金板材的拉伸性能有多大提高,但其抗蠕变性能却比Zr-4板材好得多.在400 ℃、157 MPa应力作用下,低铌新锆合金的蠕变断裂时间是常规Zr-4板材的5倍多;在137和117 MPa应力作用下,新锆合金的稳态蠕变速率大大低于常规Zr-4的.     

U-Mo合金与Zr-4合金的扩散层性质研究

本文对U-Mo合金与Zr-4合金的扩散层性质进行了研究。三明治结构的U-Mo/Zr-4扩散偶在760~800℃下包覆热轧后,保温10~66 h。采用扫描电子显微镜(SEM)分析了扩散层的形貌和厚度,采用波谱仪(WDS)分析了各元素在扩散区内的分布情况,采用X射线衍射仪(XRD)测定了扩散层的相组成。分析结果表明,即使在800℃的高温下,U-Mo/Zr-4的扩散程度依然微弱,表现出良好的相容性;U-Mo/Zr的扩散层中间出现裂纹,裂纹两侧的扩散层相组成明显不同,靠近U-Mo侧为富Mo相,其主要是以化合物ZrMo_2为基的固溶体;靠近Zr-4侧的为富Zr相,其主要是以化合物UZr_2为基的固溶体;裂纹认为是由U和Zr不等量的原子交换所造成的。     

1Cr18Ni9Ti不锈钢低周疲劳随动硬化实验研究

为了研究单调加载对1Cr18Ni9Ti不锈钢材料后继循环塑性硬化和流动特性的影响,对该材料进行了带平均应变的低周疲劳实验研究.对不同应变幅值的对称应变及非对称的应变循环进行了屈服面半径和背应力演化分析,揭示了材料的随动硬化和各向同性硬化演化对应变幅值和平均应变的依赖性.实验结果为建立循环加载和单调加载耦合的复杂加载条件下的本构模型提供了实验基础.     

Y/Ce注入对Zr-4合金高温氧化行为的影响

为了比较研究Y、Ce离子注入对Zr-4合金氧化性能的影响，探索离子注入后的改性机制，对Zr-4合金表面分别注入了不同剂量的两种离子并在500℃条件下进行空气氧化．氧化曲线表明：Y、Ce离子注入均能明显改善Zr-4合金的氧化性能，改善的程度随注入剂量的提高而增大；Ce离子注入后的改性效果略强于Y．使用XPS、GAXRD研究了注入样品高温氧化实验后的表层氧化膜成份及其相结构，探讨了Y、Ce离子注入提高Zr-4合金高温抗氧化性能的机理。     

Zr－4合金管环向性能测试研究

采用对开式拉伸法（ＮＯＬ环法），对反应堆中常用构件Ｚｒ－４合金薄壁细管，在不同温度条件下进行了环向拉伸试验。通过对拉伸曲线的修正和炉内试样颈缩处承载面积的确定，得到了Ｚｒ－４合金管在不同温度条件下，环向拉伸的真应力一真应变关系及强度、塑性指标。     

Delayed Hydride Crack Velocity of Zirconium Alloys with the Direction of an Approach to Temperature

The delayed hydride cracking (DHC) tests were conducted on Zr-2.5Nb compact tension specimens with the test temperatures reached by a heating and a cooling. The Zr-2.5Nb specimens were either furnace-cooled or water-quenched after a hydrogen charging treatment to contain 10 to 100 ppm H. On an approach to the test temperatures by a cooling, both the Zr-2.5Nb specimens showed the DHC velocity increasing with an increasing temperature over a temperature range of 100-300°C, irrespective of the cooling rate. However, on an approach to the test temperatures by heating, the furnace-cooled Zr-2.5Nb showed a DHC arrest at temperatures over 180°C and no DHC at 250°C, and the water-quenched ones did have a DHC growth, even at 250°C. Using Kim's DHC model we elucidate the DHC arrest in the furnace-cooled Zr-2.5Nb at temperatures over 180°C and the DHC growth in the water-quenched specimen, even at 250°C, upon an approach by a heating.     

Deformation behavior of cold-rolled and annealed Zr-1.5Nb and Zr-1.5Nb-S alloys

In this study, the effect of sulphur on the deformation behavior of cold rolled and annealed Zr-1.5Nb, Zr-1.5Nb-S alloys were studied. The beneficial effect of sulphur on the strengthening was observed both in the cold rolled and annealed Zr-1.5Nb-S alloys. The loss of ductility was intensified with the addition of sulphur in the annealed Zr-1.5Nb-S alloys in the region of dynamic strain aging, implying the interdependent effect of oxygen and sulphur. The activation volumes, V^∗, for the cold rolled alloys are not much different from those of annealed alloys. The activation volume, V^∗, decreased slightly with the increase of the sulphur content at room temperature and 300 °C. Insensitivity of the activation volume to the dislocation density and the decrease of the activation volume with the addition of sulfur support the suggestion linking the activation volume with the activated bulge of dislocations limited by segregation of oxygen and sulphur atoms. The higher flow stress increase with the addition of sulfur in Zr-1.5Nb alloy of the present study with the higher oxygen content (∼1600 ppm) is compatible with the suggestion of the interdependent strengthening effect of sulfur and oxygen.     

CANDU及RBMK压力管锆合金的氢致延迟断裂研究

采用紧凑拉伸试样(CT），在恒定载荷、不同氢含量、不同温度条件下，测量了CANDU堆和RBMK堆Zr-2．5Nb压力管材料氢致延迟开裂速率。用金相显微镜和扫描电镜观察断口及氢化物形貌，并测量临界应力场强度因子及开裂速率，对材料的微结构及氢化物分布进行分析。结果表明，氢致延迟断裂(DHC)生长呈阶梯状。与CANDU压力管比较，RBMK压力管的DHC开裂速率将近低一个数量级。其原因是RBMK压力管的屈服强度比CANDU压力管低得多。     

Zr-0.2Cu-xNb合金的显微组织及腐蚀行为

对Zr-0.2Cu-x Nb(质量分数x=0.2,0.5,1.0,2.5)合金进行真空β相油淬、冷轧及退火处理,并在静态高压釜中进行过热蒸汽腐蚀试验,最后采用扫描电镜和透射电镜研究了合金及其腐蚀生成的氧化膜的显微组织。结果表明,随着Nb含量的增加,Zr-0.2Cu-x Nb合金中Zr2Cu第二相的数量逐渐减少,而β-Zr第二相数量逐渐增加;合金中尺寸较小的Zr2Cu第二相对耐腐蚀性能有利;β-Zr第二相在氧化过程中会促进氧化膜微裂纹的产生,降低合金的耐腐蚀性能。Zr-0.2Cu-x Nb合金中Nb含量接近其在α-Zr中最大固溶度时,合金具有最优的耐腐蚀性能。     

Steam oxidation of Zr-1.5Nb-0.4Sn-0.2Fe-0.1Cr and Zircaloy-4 at 900-1200 °C

The steam oxidation characteristics for the Zr-1.5Nb-0.4Sn-0.2Fe-0.1Cr (HANA-4) and Zircaloy-4 claddings were elucidated at LOCA temperatures of 900-1200 °C by using a modified thermo-gravimetric analyzer. After the oxidation tests, the oxidation behaviors, oxidation rates, surface appearances, and microstructures of the as-received, as-oxidized, and burn-up simulated claddings were evaluated in this study. The high-temperature oxidation resistance of the as-received HANA-4 cladding was superior to that of the Zircaloy-4. The superior oxidation resistance of the HANA-4 cladding could be attributed to the higher Nb and the lower Sn within its cladding. The pre-oxidized layer formed at the low temperatures below 500 °C could retard the oxidation rate at the high temperatures above 900 °C. And the soundness of the pre-oxidized layer formed at a lower temperature could influence the oxidation kinetics and the rate constants during a steam oxidation at LOCA temperatures from 900 to 1200 °C.     

Effect of unloading on crack growth rate of Zr-2.5Nb tubes

Crack growth rates (CGRs) of a heat-treated Zr-2.5Nb tube were determined using compact tension specimens with 60 ppm H at 250 °C under the constant and cyclic loads where the load ratio R was changed from 0.13 to 0.68. CGR was the highest under the constant load and decreased under the cyclic load with decreasing R despite a decrease of the critical hydride length indicating the enhanced rate of hydride cracking. Hence, the decreased CGR under the cyclic load is due to unloading during the cyclic load inducing the compressive stress at the crack tip. This compressive stress suppresses hydride nucleation rate, leading it to govern the CGR, according to Kim’s new model. Evidence is provided by citing Simpson’s experiment demonstrating that unloading from 15 MPa √m decreased the CGR of a cold-worked Zr-2.5Nb tube but annealing did the reverse. This study demonstrates for the first time that the retarded CGR due to an overload during the DHC tests is understood in view of crack growth kinetics using Kim’s model.