氧化物弥散强化低活化合金的微观组织及力学性能

为了强化低活化合金(CLF-1)的高温性能,将采用Ar气超声雾化方法制备的CLF-1粉末与纳米Y₂O₃粉末混合后,经高能球磨和热等静压处理,获得氧化物弥散强化（ODS）CLF-1样品。对样品进行不同制度的热处理,并进行了微观组织分析和力学性能测试。分析结果表明,经过正火和回火处理,ODS CLF-1组织为回火马氏体,当正火温度为1 100 ℃时晶粒尺寸最为均匀。回火温度对显微组织影响不明显,但回火温度升高,维氏硬度下降。热处理后样品中观察到明显的弥散分布的Y₂O₃颗粒和位错塞积,证实了弥散强化的作用。Y₂O₃颗粒尺寸不均匀,100 nm左右的大颗粒倾向于沿晶界分布,而较小的颗粒则在晶内分布。ODS CLF-1样品具有良好的高温拉伸性能,600 ℃时抗拉强度为370 MPa,延伸率为18.5%。屈服强度和抗拉强度随热处理温度的升高而降低。     

含钆中子屏蔽材料的设计及其力学性能分析

设计了一种具有良好中子屏蔽能力、高强度及高韧性的新型中子屏蔽材料,用于吸收核电站乏燃料储存格架和乏燃料运输过程中的热中子辐射。材料通过蒙特卡罗粒子传输(输运）软件MCNP进行设计,并通过放电等离子烧结设备及热轧的方式制成了板材。MCNP模拟结果及材料热中子屏蔽测试结果表明：铝基Gd₂O₃复合材料的热中子屏蔽性能与铝基碳化硼相当。Gd₂O₃颗粒球磨后呈现μm、亚μm级甚至有些颗粒达到了nm级。随球磨时间的增加,材料的力学性能逐渐增强。X射线衍射检测发现了钆-铝合金相的生成。经TEM分析表明：材料的强化机制主要是位错强化和nm级Gd₂O₃颗粒的弥散强化,拉伸强度和伸长率分别达到了240 MPa和16%,其断口主要为韧性断裂。     

纳米Y2O3/环氧树脂复合材料辐射防护性能及正电子寿命研究

传统的屏蔽X/γ射线材料一般为铅或含铅材料，存在有毒、质量重、不易成型、价格较高等缺点，而高分子复合材料被认为是未来能够有效防护核辐射的新型材料。环氧树脂（Epoxy Resin,EP）作为基材具有诸多优点，如耐腐蚀、力学性能好、耐磨性强、绝缘性优良及耐辐照性较强等，稀土材料对20～88 keV能区的X/γ射线有比较好的屏蔽效果，能够弥补铅的弱吸收区，同时可规避铅的毒性。为验证纳米稀土三氧化二钇/环氧树脂（Y₂O₃/EP）复合材料对X/γ射线的屏蔽性能，首先采用Y₂O₃填充到环氧树脂中制备了不同氧化钇含量的Y₂O₃/EP复合材料。然后利用正电子寿命谱、X射线衍射、扫描电镜研究了材料的微观结构，用热重分析仪及差示扫描量热仪测试了材料的热稳定性，用维氏硬度计及万能拉力机测试了材料的机械性能。最后利用蒙特卡罗程序对样品的辐射防护性能进行了模拟计算。研究结果表明：Y₂O₃填充到环氧树脂中可提升复合材料的热稳定性、硬度及杨...     

α/γ相比率调控对超音速等离子喷涂Al2O3阻氚涂层微结构及性能的影响

采用超音速等离子喷涂技术在中国低活化马氏体钢表面制备不同α/γ相比率的Al₂O₃阻氚涂层,研究了α/γ相比率调控对Al₂O₃涂层微观结构、力学性能和耐电化学腐蚀性能的影响。利用掠入射X射线衍射（GIXRD）和扫描电子显微镜（SEM）表征Al₂O₃涂层的微观结构、粘结拉伸试验法和纳米压痕仪表征涂层的力学性能、动电位极化曲线法测试涂层的耐电化学腐蚀性能。研究结果显示：通过调控特征喷涂参数（CPSP）,Al₂O₃涂层中α相含量从78.6%至24.4%可控调节,且孔隙率从2.8%降低至1.5%;α相含量为78.6%的Al₂O₃涂层硬度为(11.500±0.575) GPa,约为高γ相含量(75.6%)涂层的2倍;且高α相含量(78.6%)涂层的腐蚀电流密度较高γ相含量(75.6%)涂层的腐蚀电流密度低1个数量级。以上结果表明,高α相含量(78.6%)的Al₂O₃涂层具有更优异的力学性能、耐电化学腐蚀性能以及耐Cl^-扩散穿透能力,具有应用于聚变堆结构材料表面阻氚涂层的潜能。     

FCM燃料压水堆弥散可燃毒物中子学分析

为将全陶瓷微胶囊封装（FCM）燃料应用于小型压水堆,对FCM燃料组件开展了可燃毒物中子学设计与分析。通过寿期初引入负反应性、寿期内消耗速率和寿期末残留3个方面,对弥散在SiC基体中的弥散型可燃毒物Gd₂O₃、Er₂O₃、Sm₂O₃、Eu₂O₃、Dy₂O₃及HfO₂进行评价。FCM燃料中TRISO颗粒核芯直径达800 μm,燃料颗粒自屏效应强烈,在RMC程序中引入随机介质计算功能,对FCM燃料进行随机几何建模,保证了反应性计算精度。分析表明：Er₂O₃可作为FCM燃料堆芯的候选可燃毒物,Gd₂O₃和Eu₂O₃需结合堆芯开展进一步研究,Sm₂O₃、Dy₂O₃及HfO₂的反应性惩罚过大,不适合作为FCM燃料可燃毒物。     

空间离散对弥散颗粒燃料燃耗计算的影响

单栅元燃耗计算是全堆芯燃耗计算的基础，栅元空间离散对燃耗计算的结果有显著影响。弥散颗粒燃料由于双重非均匀性的存在，空间离散的情况更为复杂。本文基于ALPHA组件程序，分析了颗粒在平源区上归类的宏观离散方案与颗粒内部细分燃耗区的微观离散方案对弥散颗粒燃料燃耗计算的影响。算例包括无毒物的UC颗粒单栅元，含Gd₂O₃层的QUADRISO颗粒单栅元和含UC颗粒与Gd₂O₃毒物颗粒的双颗粒单栅元。数值结果表明，无毒物栅元宏观需分3圈以上，含Gd₂O₃栅元宏观需分5圈以上；无毒物算例微观不需要分圈，含Gd₂O₃层的QUADRISO颗粒需在微观燃料区细分2圈，双颗粒问题的Gd₂O₃毒物颗粒微观需分12～15圈。     

P2O5对模拟高放玻璃固化体析晶和抗浸出性能的影响

针对高放废液硼硅酸盐玻璃固化体易析出辉石晶相的问题,本文采用P₂O₅部分替代硼硅酸盐基础玻璃配方中的MgO和CaO,研究了P₂O₅掺量(质量分数为0～8%)对玻璃固化体析晶和抗浸出性能的影响。结果表明,当P₂O₅掺量为0～3%时,样品为无定形态,在850℃热处理6 h后,P₂O₅掺量为0～2%的样品主要析出辉石晶相,而P₂O₅掺量为3%的样品析出了少量硅酸钙晶相,辉石晶相基本消失;当P₂O₅掺量高于3%时,样品析出球形Na₃Ca₆(PO₄)₅晶体,且析晶度随P₂O₅掺量的增加而升高。²⁹Si MAS NMR和¹¹BMAS NMR分析表明,随着P_...     

基于深度神经网络的ODS合金辐照硬化预测

氧化物弥散强化(ODS)合金作为第4代先进堆结构材料和聚变堆第一壁结构材料的候选材料,其抗辐照性能仍是制约其在快堆和聚变堆领域应用的关键技术难题。本文通过收集ODS合金的成分、固化和热处理工艺、辐照条件、测试条件（包括温度等）及屈服强度等数据约570条,并对数据进行清洗及重要属性的筛选,采用机器学习中反向传播的深度神经网络方法,尝试构建了Cr、Y₂O₃等关键成分与ODS合金中子辐照硬化的关联性,获得针对ODS合金辐照硬化的性能预测。结果表明：Cr含量约为6%、Y₂O₃添加量约为0.2%时,ODS合金的辐照硬化程度降低,同时Ti的添加有利于ODS合金辐照硬化程度的降低,而添加Al则会加剧其辐照硬化。据此,后续可得出一定辐照条件下,辐照硬化程度更低的ODS合金成分设计方案。     

钙含量对钙钛锆石-钡硼硅酸盐玻璃陶瓷结构的影响

采用熔融-热处理工艺制备SiO₂-Na₂O-B₂O₃-BaO-CaO-TiO₂-ZrO₂体系玻璃陶瓷,利用差热分析法（DTA）、傅氏转换红外线光谱分析仪（FTIR）、X射线衍射仪（XRD）、扫描电子显微镜（SEM）等技术手段研究了晶核剂（CaO、TiO₂和ZrO₂）总含量为45%时,不同钙含量（CaO∶TiO₂∶ZrO₂=x∶2∶1（摩尔比）,x=0.5～6）对玻璃陶瓷晶相和显微结构的影响,并采用粉末静态浸泡法（PCT）测试了C₂（即x=2）玻璃陶瓷样品的抗浸出性能。结果表明：玻璃网络结构主要由［SiO₄］、［BO₃］和［BO₄］构成,随着Ca含量的增加,更多的B以［BO₄］加入玻璃网络中,玻璃转变温度T_g逐渐升高,放热峰温度逐渐降低,但峰强逐渐增高;x＜2时,样品中除CaZrTi₂O₇晶相外还有其他晶相（如TiO₂和ZrO₂）出现;当x=2和4时,样品中只有单一的CaZrTi₂O₇晶相;x=6时,有星状的CaZrTi₂O₇和柱状的CaTiO₃晶相生成。PCT实验结果表明：B、Na、Ca元素的归一化浸出率随浸泡时间的增加而降低,并在28 d后保持不变,分别为8.4、7.8、2.2 mg/(m²•d),与硼硅酸盐玻璃固化体浸出率处于同一数量级。     

含铝奥氏体耐热钢在超临界二氧化碳中的腐蚀行为

研究了20Cr-25Ni合金和一种新型结构材料含铝的奥氏体耐热钢(AFA钢)在600℃/20 MPa的超临界二氧化碳(S-CO₂)环境中的腐蚀行为,并对2种合金的氧化膜形貌、成分和结构进行分析。研究发现,20Cr-25Ni合金出现明显的腐蚀增重增长趋势,表现出“抛物线”上升规律;AFA钢腐蚀增重趋势缓慢,腐蚀1000 h后仅为2.11 mg/dm²。20Cr-25Ni合金表面出现粗大的氧化产物,随腐蚀时间延长,AFA钢的氧化膜始终保持致密、连续。通过氧化膜的截面形貌分析发现,20Cr-25Ni合金腐蚀后具有两层氧化膜结构,主要由Fe₃O₄和FeCr₂O4_氧化层以及少量尖晶石组成。而AFA钢中出现了3层氧化膜结构,中间和最内层分别为Cr₂O₃和Al₂O₃氧化膜,最外层分布了一层不连续的FeCr₂O₄尖晶石氧化物。由于形成了致密的...     

Post irradiation examination of uranium inclusions in inert matrices.

The inert matrix materials CeO₂, MgO, Y₂O₃, MgAl₂O₄ and Y₃Al₅O₁₂ were selected as candidates for inert matrices for the EFTTRA²-T3 neutron irradiation experiment. Most targets contain 20% enriched ²³⁵U fissile inclusions with an average size of roughly 150 μm. The volume fraction of the fissile phase is either 2.5 vol% UO₂ or 19.6 vol% of Y_5.78UO_x in the inert matrices. The samples were irradiated for 198.9 full power days in the High Flux Reactor in Petten. The calculated burn-up is between 17.3 and 19.5% FIMA. The temperature of the cladding was kept at 600 ± 25 K. A dimensional change of at least +5 % is measured after neutron irradiation for Y₃Al₅O₁₂ and MgAl₂O₄ with macro dispersions of UO₂; the other targets with a macro dispersion of UO₂ show a volume change of less than + 1 vol%. The fractional release of the fission gas Xe is more than 40% for the MgAl₂O₄ and Y₃Al₅O₁₂ matrices with a macro dispersion of UO₂, the other targets show a fractional release of Xe of less than 15%. Cracks are observed in MgO and MgAl₂O₄ targets which is possibly related to the stress caused by swelling of the UO₂ inclusions.     

Mechanical and thermomechanical properties of commercially pure chromium and chromium alloys

The mechanical and thermal properties of commercially pure chromium and the chromium-based alloys Cr–5Fe–1Y₂O₃ and Cr–44Fe–5Al–0.3Ti–0.5Y₂O₃ have been investigated in order to determine the thermal stress factor of these materials and to assess their capability to withstand high-thermal loads in fusion applications. Especially the alloy Cr–5Fe–1Y₂O₃ combines sufficient mechanical strength at temperatures up to 1000 °C, high-thermal conductivity and a low-thermal expansion coefficient to yield the lowest thermal stress factor of all metallic candidate materials for first wall and blanket applications. The high-ductile-to-brittle transition temperature may lead to a rather high value for the lower operation-temperature limit.     

Fe-Al/Al2O3阻氚涂层热处理条件对HR-2不锈钢力学性能影响

采用室温力学拉伸试验、显微硬度测试、X射线衍射及组织观察等方法研究了"室温熔盐电镀铝+热处理+选择性氧化"工艺路线制备Fe-Al/Al2 O3阻氚涂层热处理过程对HR-2奥氏体不锈钢力学性能及显微组织的影响.结果表明:经热处理后的HR-2不锈钢仍然保持奥氏体组织;980℃热处理180 min时抗拉强度为580.48 M...     

Effects of xenon implantation in spinel-zirconia/ceria composites

Two prethinned spinel specimens containing either Y_0.15Zr_0.85O₂ or Ce_0.5Zr_0.5O₂ particles were implanted with 200–400 keV Xe ions at 873 K using the IVEM-Tandem Facility at Argonne National Laboratory. In situ transmission electron microscopy (TEM) was conducted during the implantation in order to follow the evolution of the microstructure. At an ion fluence between 2.4x10²⁰ to 3x10²⁰ m⁻² (up to 50 dpa and 4.7 at %), large Xe bubbles of 50–100 nm developed at the boundaries of the small oxide particles, while a high density of dislocation loops (up to 8 nm in diameter) and much smaller bubbles (up to 4 nm in diameter) formed in the spinel matrix. No large bubbles were observed at the boundaries between the spinel grains. These results suggest that the boundaries between spinel and oxide particles are preferred sites for fission gas accumulation.     

B4C-Al中子吸收材料拉伸性能及断裂机理

为评价粉末冶金法制备的B₄C-Al中子吸收材料的力学性能,采用静态拉伸的试验方法研究板材的室温及高温拉伸性能,并运用扫描电镜进行断口形貌观察,对复合材料的断裂机理进行讨论。研究表明：室温下,B₄C质量分数为30%的B₄C-Al复合板材的屈服强度为200 MPa,抗拉强度为250 MPa,断后伸长率为2.5%;在实验范围内,随着温度的升高,材料的抗拉强度和屈服强度下降,并趋于一致,材料的断后伸长率增加并达到最大值。复合材料的断裂宏观表现为脆性断裂,断裂是由基体内微孔隙成核、聚集和基体与增强相的界面脱粘断裂的共同作用造成的。     

Measurement of the cross sections for the reactions Cr(n,2n)Cr, Zn(n,2n)Zn, Y(n,2n)Y and Zr(n,2n)Zr from 13.5 to 14.8 MeV

Cross section measurements for the reactions ⁵²Cr(n,2n)⁵¹Cr, ⁶⁶Zn(n,2n)⁶⁵Zn, ⁸⁹Y(n,2n)⁸⁸Y and ⁹⁶Zr(n,2n)⁹⁵Zr were carried out in the neutron energy range 13.47–14.79 MeV applying the activation technique. Neutrons were produced via the T(d,n)⁴He reaction, making use of the variation of neutron energy with the emission angle. The neutron fluences incident on the samples were determined relative to the well-evaluated cross section for the reaction ⁹³Nb(n,2n)^92mNb.

The induced γ-ray activities of the irradiated Zn, Zr and Y₂O₃ samples and their monitor foils were measured by means of a calibrated Ge(Li) γ-ray detector at the KFI, Debrecen. At the IRK, Vienna, relative γ-ray measurements using a high-purity Ge detector were combined with integral γ-ray counting by means of a NaI(TI) well-type detector on the Cr, Zn and Zr foils of highest activity and on some Nb monitor foils; integral γ-ray counting only was applied in the case of the Y₂O₃ samples. All necessary corrections were taken into account.

The results are compared to the corresponding results of cross section measurements published in the literature. The uncertainties obtained in this work are considerably smaller in most cases than the uncertainties given by other authors.