慢正电子束研究质子辐照CLAM钢产生的缺陷及其退火行为

为了研究中国低活化马氏体CLAM钢的辐照损伤机理,本文利用慢正电子技术研究了质子辐照CLAM钢时所产生的缺陷及其退火回复行为,发现辐照在材料中产生空位团数密度随质子注量增加而增多,而其尺度增大并不明显.辐照仅产生原子尺度的空位和空位团,400℃退火可以使缺陷很好地消除.此外分析了硅对CLAM钢辐照性能的影响,实验上没有观察到硅的添加抑制了质子辐照缺陷的产生.     

430℃下2.98dpa中子辐照后CLAM钢的拉伸和冲击性能

利用高通量工程试验堆HFETR开展了CLAM钢430℃下2.98dpa的中子辐照实验,通过辐照前后拉伸和冲击性能测试与对比分析,研究了CLAM钢的中子辐照硬化和脆化效应。结果显示,CLAM钢辐照后室温测试的抗拉强度和屈服强度分别为710 MPa和615 MPa,较辐照前分别下降16 MPa和-0.5MPa,总延伸率减小1%,断面收缩率下降4%,保持良好的强度、塑性和韧性。冲击测试表明,CLAM钢辐照前后韧脆转变温度基本相同,上平台能量无明显变化,约为217J,未出现明显辐照脆化。CLAM钢的抗辐照性能略优于其他低活化铁素体/马氏体RAFM钢在类似辐照条件下的性能。     

硅对9Cr-1.5WVTa低活化马氏体钢力学性能的影响

基于中国正在研究的聚变堆用9Cr-1.5WVTa低活化马氏体钢(CLAM钢),研究了添加合金元素硅对CLAM钢力学性能的影响。结果表明,添加0.2%Si使得CLAM钢的抗拉强度和屈服强度明显提高,钢的塑性和冲击韧性同时也得到一定提高,其中,韧脆转变温度(DBTT)由-13℃降至-30℃。未添加和添加0.29%Si的CLAM钢均为全马氏体组织,无δ铁素体存在。硅的添加使得9Cr-1.5WVTaSi钢的晶粒细化,从而提高了钢的拉伸和冲击性能。     

1.61 dpa/300℃中子辐照后CLAM钢的硬化和脆化行为

较低温度(350℃)下,反应堆结构材料的中子辐照硬化与脆化行为一直是其核工程应用中关注的热点问题之一。低活化铁素体/马氏体钢(RAFM)是国际热核聚变堆实验包层模块(ITER-TBM)首选结构材料,其在寿期内受到的中子辐照累积剂量不超过3 dpa,服役温度300~500℃。为推进具有我国自主知识产权的中国低活化钢-CLAM钢在ITER中国实验包层模块(ITER-CN-TBM)中的应用,本文通过开展1.61 dpa/300℃中子辐照前后CLAM钢拉伸性能和冲击性能测试以及与国际同类低活化钢相近辐照条件下的性能数据进行对比分析,研究了中子辐照后CLAM钢的硬化和脆化行为。结果表明,CLAM钢辐照后在室温测试时的抗拉强度和屈服强度分别为692 MPa和596 MPa,相比辐照前分别增加了29 MPa和56 MPa,表现出一定程度的辐照硬化。辐照后的韧脆转变温度DBTT相比辐照前增加了56℃,出现辐照脆化现象。与国际同类低活化钢在相近辐照条件下的测试结果对比分析,表明CLAM钢具有相对优异的抗中子辐照能力。     

合金添加剂Si和Ti对316不锈钢辐照肿胀作用的研究

用ＨＶＥＭ在１ＭｅＶ和５５０℃下原位研究了Ｓｉ和Ｔｉ对３１６不锈钢照肿胀的影响。含１％Ｓｉ的３１６钢在辐照剂量≤１１ｄｐａ时作含０．１％Ｔｉ的一样，能强烈抑制辐照肿胀。但在〉１１ｄｐａ后，含１％Ｓｉ的３１６钢肿胀率远大于未含添加剂的对比钢样吕，含０．５％Ｔｉ能完全抑制辐照空洞产生，但诱导了Ｔｉ析出物，１％Ｓｉ的３１６钢肿胀率远大于未含添加剂的对比钢样品，含０．５％Ｔｉ能完全抑制辐照空洞产生，但诱导     

500℃下中国低活化马氏体钢电子辐照缺陷行为的研究

利用超高压透射电子显微镜在500℃对两种不同成分的CLAM钢进行了小剂量的辐照实验,研究CLAM钢的辐照效应.发现在高能电子的辐照下,1号CLAM钢的微观结构发生了变化,产生了大量的位错环,研究了位错环形核和长大的规律;2号CLAM钢的微观结构也发生了变化,先产生位错环,而后形成了位错网络.     

聚变驱动次临界堆第一壁材料辐照损伤的初步研究

介绍了中子对材料的辐照损伤原理及化合物原子平均离位(DPA)截面计算方法;使用辐照损伤计算程序SPECTER计算了聚变驱动次临界堆(FDS-I)第一壁材料CLAM钢的辐照损伤参数,并将CLAM钢的辐照损伤计算结果与相同条件下316SS、SiC等聚变堆结构材料的计算结果进行了比较.     

12Cr-ODS钢中氧化物强化相（Y2O3）辐照损伤行为研究

本文采用电子束（e^－） 氦离子（He⁺）、氢离子（H⁺）束同时复合辐照方式研究12Cr-ODS铁素体钢中氧化物弥散强化相（Y₂O₃）辐照损伤行为,对不同辐照方式下辐照区内的氧化物形貌变化进行原位观察。研究结果表明,15dpa辐照后,氧化物周围出现微小高密度空洞,相界面变得不规则,氧化物在此特定条件下发生体积收缩或长大,尺寸有少量变化,但无明显溶解现象,对钢的性能不会产生影响。     

硅对CLAM钢微观结构和力学性能的影响

文章研究了合金元素硅对CLAM钢的力学性能和微观结构的影响。实验表明，在CLAM钢中添加0.2％的Si会使其屈服强度和抗拉强度明显提高，同时使CLAM钢的韧脆转变温度升高，韧性降低。在光学显微镜下观察，CLAM钢呈现回火马氏体组织，Si的添加使奥氏体晶粒细化，致使CLAM钢的强度升高、韧性降低。在透射电子显微镜下观察，回火板条马氏体是其主要结构，存在针状和颗粒状两种形态的碳化物;利用透射电子显微镜选区衍射方法可知，呈颗粒状的碳化物是M23C6型碳化物。Si的添加使马氏体板条的宽度变小。     

可移动式除氚器的现场应用试验

在现场闭路循环工作模式下，采用中国辐射防护研究院研制的小型可移动式除氚器对微量(（0.5~1）×10^-6)气态氚进行脱氚试验。试验结果表明：催化床在450℃工作温度下，空气闭路循环流量为3.8m³/h时，除氚器可在114min内将1m³密封不锈钢罐空气中的氚浓度由4.62×10⁶Bq/L降至4.62×10³Bq/L。同时，论证了除氚器在现场使用的适应性与安全性，并对其研制和现场性能试验中发现的技术问题进行了论述。     

Void swelling in a 9Cr ferritic/martensitic steel irradiated with energetic Ne-ions at elevated temperatures

In this work the void swelling behavior of a 9Cr ferritic/martensitic steel irradiated with energetic Ne-ions is studied. Specimens of Grade 92 steel (a 9%Cr ferritic/martensitic steel) were subjected to an irradiation of ²⁰Ne-ions (with 122 MeV) to successively increasing damage levels of 1, 5 and 10 dpa at a damage peak at 440 and 570 °C, respectively. And another specimen was irradiated at a temperature ramp condition (high flux condition) with the temperature increasing from 440 up to 630 °C during the irradiation. Cross-sectional microstructures were investigated with a transmission electron microscopy (TEM). A high concentration of cavities was observed in the peak damage region in the Grade 92 steel irradiated to 5 dpa, and higher doses. The concentration and mean size of the cavities showed a strong dependence on the dose and irradiation temperature. Enhanced growth of the cavities at the grain boundaries, especially at the grain boundary junctions, was observed. The void swelling behavior in similar 9Cr steels irradiated at different conditions are discussed by using a classic void formation theory.     

Xe~+离子辐照诱导国产T91及316Ti钢微结构变化研究

对国产T91及316Ti钢进行室温下200keV的Xe~+离子辐照,使用X射线衍射(XRD)、透射电镜(TEM)等检测方法研究不同损伤剂量下辐照对材料相的稳定性和微观结构变化的影响。研究结果表明:T91钢辐照后未发生明显相变,而316Ti发生了γ(FCC)→α(BCC)的马氏体相变,且随辐照损伤剂量的增加,α相含量增加,相变的主要驱动力为辐照离子在辐照层的聚集从而产生的剪切应力;T91钢中的M_(23)C_6颗粒随辐照损伤剂量的增加,非晶化越来越明显,主要是由于辐照粒子的轰击削弱了M_(23)C_6颗粒晶格的稳定性,晶格塌陷成为非晶状态;316Ti钢在较低辐照损伤剂量(4.6dpa)下出现黑斑结构,而在高辐照损伤剂量(37.1dpa)下黑斑结构进一步聚集形成位错环。     

Void formation in solution-treated aisi 316 and 321 stainless steels under 46.5 mev ni6+ irradiation

The swelling and radiation damage structure developed in solution-treated 316 and 321 stainless steels bombarded by 46.5 MeV Ni⁶⁺ ions in the Variable Energy Cyclotron (VEC) have been determined. Foils were pre-injected with 10^?5 a/a He at room temperature and subsequently bombarded by Ni⁶⁺ ions in the temperature range 450–750°C at a damage rate of 1–3 × 10^?3 dpa per second to doses up to 300 dpa and specimens from the foils were examined by transmission electron microscopy. The data obtained were compared with data from other experiments aimed at simulating the fast-neutron irradiation of 316 and 321 steels, in particular previous work with 20 MeV C²⁺ ions and with data on fast-reactor bombarded material. The swelling rates in Ni-ion bombarded specimens were about a factor two less than those in C-ion bombarded specimens and in good agreement with swelling rates in 5 MeV Ni⁺- and neutron-bombarded material. The peak swelling temperature after a dose of 40 dpa was 650°C in 316 steel and 625°C in 321 steel where the swelling was about 5.8% and 4.6% respectively.     

注氘低活化马氏体钢在电子辐照下的缺陷行为

低活化铁素体/马氏体(RAFM)钢被视为国际热核聚变反应堆以及聚变反应堆的第1壁候选结构材料之一,很多国家均在研究不同的RAFM钢,中国低活化马氏体(CLAM)钢的研究亦正在进行。核聚变会产生氢、氦、氘及氚,这些气体元素与辐照缺陷结合在一起,对材料的辐照性能会产生较大影响。本文对注氘后不同温度下的辐照后微观结构进行研究。试验利用日本北海道大学的JEOL-1300高压电子显微镜研究注氘CLAM钢从室温到873K在1250keV电子辐照下的微观结构变化。研究结果表明,在电子辐照下,注氘产生的缺陷团会出现消失和长大两种现象,意味着间隙型与空位型位错环在注氘过程中同时产生。并研究了注氘产生的空洞。     

多层介质/金属紫外滤光膜系的辐照损伤特性

利用电子束蒸发方法制备用于BaF₂晶体慢成分滤光的多层介质/金属紫外滤光膜系。在γ射线、中子和激光辐照环境中研究薄膜的损伤特性。结果表明：薄膜对γ射线和中子具有优良的耐辐照特性；在激光辐照环境中，薄膜的激光损伤阈值受多层薄膜中金属层的影响，激光入射时，最先辐照到的金属层的厚度决定了多层薄膜的耐激光辐照损伤特性。     

Observation and analysis of damage structure in Al and Al/Mg (N4) alloy after irradiation with 100 and 400 keV aluminium ions

A comparative TEM study has been made of ion irradiation damage structure in pure aluminium, commercial aluminium (grade 1100) and in a modified N4 (Al/2.95% Mg) alloy of the type used in the construction of the calandria of the Winfrith prototype SGHW Reactor. Atom displacements equivalent to many years neutron irradiation were simulated by bombardment with 100 and 400 keV Al⁺ ions to doses of up to 200 dpa at temperatures between 30 and 250°C. Dynamic observations of damage formation were made during irradiation with 100 keV ions in a linked heavy-ion accelerator/200 keV electron microscope, and further results were obtained by 400 keV Al⁺ ion bombardment in a Cockcroft-Walton accelerator. Dislocation structure and voids were seen in aluminium irradiated with 100 and 400 keV A1⁺ at temperatures between 30 and 250°C. Void swelling of 8.7% at 104 dpa was a maximum at 1̃50°C in type 1100 aluminium. No voids were found at temperatures μ 250°C. No voids were seen in the Al/Mg N4 alloy after bombardments up to 200 dpa with 100 keV A1⁺, and 150 dpa with 400 keV Al⁺ at temperatures between 50 and 170°C. The void-resistant property is consistent with observations in the USA of neutron-irradiated 5052 Al alloy which has a similar magnesium content to the modified N4 alloy. The 1100 alloy and N4 results have been analysed using the rate theory of swelling. The absence of voids in the N4 alloy indicates an effective vacancy annihilation mechanism, which possibly occurs at small precipitates formed during irradiation.     

Proton irradiation emulation of PWR neutron damage microstructures in solution annealed 304 and cold-worked 316 stainless steels

Solution annealed (SA) 304 and cold-worked (CW) 316 austenitic stainless steels were pre-implanted with helium and were irradiated with protons in order to study the potential effects of helium, irradiation dose, and irradiation temperature on microstructural evolution, especially void swelling, with relevance to the behavior of austenitic core internals in pressurized water reactors (PWRs). These steels were irradiated with 1 MeV protons to doses between 1 and 10 dpa at 300 °C both with or without 15 appm helium pre-implanted at ∼100 °C. They were also irradiated at 340 °C, but only after 15 appm helium pre-implantation. Small heterogeneously distributed voids were observed in both alloys irradiated at 300 °C, but only after helium pre-implantation. The pre-implanted steels irradiated at 340 °C exhibited homogenous void formation, suggesting effects of both helium and irradiation temperature on void nucleation. Voids developed sooner in the SA304 alloy than CW316 alloy at 300 and 340 °C, consistent with the behavior observed at higher temperatures (>370 °C) for similar steels irradiated in the EBR-II fast reactor. The development of the Frank loop microstructure was similar in both alloys, and was only marginally affected by pre-implanted helium. Loop densities were insensitive to dose and irradiation temperature, and were decreased by helium; loop sizes increased with dose up to about 5.5 dpa and were not affected by the pre-implanted helium. Comparison with microstructures produced by neutron irradiation suggests that this method of helium pre-implantation and proton irradiation emulates neutron irradiation under PWR conditions.