Al-B4C复合材料在硼酸溶液中腐蚀机理研究

采用硼酸溶液模拟乏燃料贮存水池环境,研究Al-B₄C复合材料在其中的腐蚀行为。用SEM、EDS观测腐蚀试样的微观形貌,用XRD测试腐蚀前后试样的物相,并测试腐蚀过程中试样的干重。结果表明：材料中的Al是引起腐蚀的主要因素;0~500 ppm硼酸溶液中,试样腐蚀增重,在表面生成斜晶结构的Al(OH)₃氧化膜,对材料起一定保护作用;2 500 ppm硼酸溶液中,试样腐蚀增重,在表面沉积非晶结构的Al(OH)₃絮状腐蚀产物;10 000~25 000 ppm硼酸溶液中,试样腐蚀失重,表面局部微小区域可观察到龟裂和腐蚀“坑”生成。材料抗腐蚀性能随溶液硼酸浓度的增加而降低,欲提高材料抗腐蚀性能,需对其进行表面保护处理。     

钛合金在硼、锂介质中的缝隙腐蚀行为分析

钛合金作为新型蒸汽发生器的主要结构材料，其耐缝隙腐蚀性能受到关注，而钛合金在硼、锂介质中的缝隙腐蚀行为研究较少。本文采用微型腐蚀回路对钛合金TA16和TA17在硼、锂介质中的5000 h缝隙腐蚀行为进行了研究，获得了2种材料的缝隙腐蚀敏感性，并对试验后钛合金氧化膜成分和结构进行了分析。结果表明：在缝隙腐蚀模拟件上未观察到缝隙腐蚀现象，TA16、TA17在硼、锂介质中对缝隙腐蚀不敏感；模拟件缝隙内、外的氧化物存在一定差异，缝隙外的颗粒状微晶钛铁矿(FeTiO₃)与钛合金缝隙腐蚀无关。     

反应堆压力容器密封面材料非正常工况下的腐蚀性能研究

针对压力容器密封面材料在核工程应用中发生的腐蚀问题,研究了反应堆压力容器密封面材料非正常工况下的腐蚀性能.利用静态高压釜研究308L不锈钢在不同Clˉ浓度条件下的腐蚀行为,采用金相显微镜和扫描电镜( SEM)对样品进行观察和分析.结果表明,在270℃、5.5 MPa条件下,Clˉ浓度低于1 mg/L时308L不锈钢没有发生点腐蚀、缝隙腐蚀和应力腐蚀;随着Clˉ浓度提高,308L不锈钢对点腐蚀、缝隙腐蚀和应力腐蚀的敏感性显著增加.     

硝酸介质中铀矿冶设备表面放射性污染的规律

为了掌握铀矿冶生产实践中常用设备材质经放射性污染后表面活度的变化规律，研究了不锈钢、有机玻璃、橡胶3种材质经不同浓度的硝酸铀酰溶液连续浸泡26 d后，样品表面活度、表面形貌及铀的存在形式等变化特征。结果表明：在26 d内，当铀溶液质量浓度为10.22 mg/L时，3种材质表面活度随浸泡时间增加变化不显著，当溶液铀质量浓度分别为563.58 mg/L、25.54 g/L时，各材质表面活度值均随浸泡时间增加逐渐增大。此外，3种材质表面活度从大到小依次是橡胶>不锈钢>有机玻璃。样品表面活度的增加主要是由于样品被腐蚀，导致铀在样品表面的附着沉积引起，并且表面的铀主要以UO₂(NO₃)₂•6H₂O及少量UO₃的形式存在。     

硝酸介质中铀矿冶设备表面放射性污染的规律

为了掌握铀矿冶生产实践中常用设备材质经放射性污染后表面活度的变化规律，研究了不锈钢、有机玻璃、橡胶3种材质经不同浓度的硝酸铀酰溶液连续浸泡26 d后，样品表面活度、表面形貌及铀的存在形式等变化特征。结果表明：在26 d内，当铀溶液质量浓度为10.22 mg/L时，3种材质表面活度随浸泡时间增加变化不显著，当溶液铀质量浓度分别为563.58 mg/L、25.54 g/L时，各材质表面活度值均随浸泡时间增加逐渐增大。此外，3种材质表面活度从大到小依次是橡胶>不锈钢>有机玻璃。样品表面活度的增加主要是由于样品被腐蚀，导致铀在样品表面的附着沉积引起，并且表面的铀主要以UO₂(NO₃)₂•6H₂O及少量UO₃的形式存在。     

不锈钢堆焊层在Cl-溶液中的腐蚀性能研究

采用浸泡腐蚀试验方法,研究了不锈钢堆焊层材料在Cl^-溶液中的腐蚀情况,并通过金相显微镜、扫描电子显微镜、能谱分析观察表面形貌。研究表明,室温条件下堆焊层材料未发生任何腐蚀。在高温条件下,Cl^-的存在诱导了点腐蚀的发生,且随着Cl^-浓度的增加,点腐蚀加剧;较高浓度的Cl^-可导致缝隙内金属元素Cr的流失,缝隙腐蚀加深;应力腐蚀裂纹有沿晶开裂的特征,应力腐蚀敏感性随Cl^-浓度的增加有提高的趋势。     

N2气氛下氨水溶液γ辐射分解行为

某些压水堆中使用氨及其分解产生的H₂抑制H₂O₂、O₂和·OH等氧化性物种的浓度,在保持一回路的还原性化学环境的同时调节冷却剂pH,以减轻结构材料的腐蚀。本工作为了研究脱氧氨水溶液在辐射场中的分解行为,针对其在γ场中的辐解过程进行了实验研究,重点考察了N₂压强、气相与液相体积之比和温度对氨水溶液辐解的影响,测定了剩余氨、H₂和氮氧化物(NO₂^-和NO₃^-)的浓度及溶液的pH。结果表明：N₂压强(0.5～5.0 MPa)及气液体积比的变化未对氨的分解和氮氧化物的生成造成影响,吸收剂量为28.8 kGy时,辐解产生的氮氧化物浓度约为1 mg/L,但N₂压强和气液体积比的增加会显著降低H₂的浓度。温度由25℃升至200℃时,氨的分解过程将大幅放缓,吸收剂量为14.4 kGy时,30 mg/L氨水中氨的分解比例由...     

焊接残余应力对316LN不锈钢应力腐蚀裂纹扩展速率的影响

核电站不锈钢管道焊接过程中引入的残余应力对焊接接头的应力腐蚀开裂性能有较大影响。本文针对一AP1000主管道316LN不锈钢焊接模拟件进行残余应力分析和应力腐蚀裂纹扩展速率测量,得到了焊后原始状态和去应力热处理状态的焊接热影响区材料在高温高压水中的应力腐蚀裂纹扩展速率。实验结果表明,焊接残余应力明显提高了热影响区的应力腐蚀裂纹扩展速率,且在含氢的压水堆一回路正常水化学下焊接残余应力的影响更加显著。     

UiO-66-(COOH)2的合成及其对锂同位素吸附分离性能研究

为研究金属有机骨架材料对⁷Li的吸附分离性能,本研以水作为溶剂,四氯化锆和均苯四甲酸为起始原料,采用水热法合成金属有机骨架材料UiO-66-(COOH)₂,对合成材料的形貌、孔径、热稳定性等进行表征与分析;通过静态吸附实验探讨吸附时间、反应温度、溶液浓度对UiO-66-(COOH)₂锂离子吸附性能及同位素分离因子的影响;并对Li⁺浓度、⁶Li/⁷Li同位素丰度进行测定。结果表明,UiO-66-(COOH)₂可实现对锂的吸附以及⁷Li的分离,且在293 K Li₂CO₃溶液中,每0.05 g UiO-66-(COOH)₂对10 mL 0.05 mol/L Li₂CO₃进行4 h的静态吸附,最大吸附量Q为9.53 mg/g,分离因子S（⁷Li/⁶Li）为1.019 54。研究结果为⁷Li的分离提供了新途径。     

Cl~-和Cu~(2+)对国产690合金应力腐蚀性能的影响

采用慢应变速率拉伸(SSRT)的方法,研究国产690合金分别在316℃含100 mg/L Cl-、1000 mg/L Cu2+以及100 mg/L Cl-与1000 mg/L Cu2+混合溶液中的应力腐蚀行为。通过激光共聚焦显微镜和扫描电镜观察断裂后试样的表面、断口以及纵剖面的微观形貌。结果表明:国产690合金在同时含Cl-与Cu2+的溶液中具有较高的应力腐蚀敏感性;断裂试样表面出现了大量的腐蚀坑,断口呈明显的脆性断裂特征,且在表面蚀坑的底部发现了沿晶应力腐蚀裂纹的萌生。由此证明Cl-与Cu2+对国产690合金应力腐蚀的协同作用,并初步探讨了其作用机理。     

ATF用ODS-FeCrAl管材的耐腐蚀性能研究

针对尺寸为Φ9.5 mm×0.3 mm的氧化物弥散强化（ODS）-FeCrAl管材在360℃/18.6 MPa/100 d静态水溶液、360℃/18.6 MPa/1200 ppm B+2.2 ppm Li/100 d（1 ppm=10?6）动态水溶液、1200℃/0.1 MPa/8 h水蒸气中的腐蚀行为进行研究,利用扫描电镜（SEM）、X射线光电子能谱（XPS）和X射线衍射（XRD）等检测方法,分析管材表面氧化膜形貌、组织结构和元素分布。结果表明,360 ℃水溶液中极低的氧浓度使得ODS-FeCrAl管材在静态和动态水溶液的腐蚀产物主要是Fe₃O₄,质量增重分别为0.036 mg/cm2和0.36 mg/cm2,氧化膜厚度分别为管壁厚度的0.072%和0.72%;1200℃水蒸气腐蚀时,高温和充足的氧含量促使管材表面生成平均厚度为2.34 μm的α-Al₂O₃膜,延缓基体进一步氧化;腐蚀后的氧化膜表面和截面未发现开裂、孔洞等缺陷。与Zr-4管材参比试样相比,ODS-FeCrAl管材表现出优异的高温抗氧化、抗腐蚀性能。      

Post-reactor studies of fuel assemblies and a control-and-safety system channel of the reactor in the first in the world nuclear power plant

The results of post-reactor materials engineering studies of fuel assemblies and control-and-safety system channels, which were unsealed in the reactor of the world’s first nuclear power plant in the period from 1987 to 1998, are presented. It is established that the destruction of the fuel element, fuel-assembly tubes and a channel of the control-and-safety system was due to the formation of through transcrystallite brittle cracks and corrosion foci on the outer side of the tubes and outer cladding of the fuel elements which is in contact with the gas medium of the reactor. Chlorine was discovered on the outer surface of the outer cladding of the fuel elements in the damaged zone. The maximum chlorine concentration was observed in cracks and pits. The presence of the chlorine ion is due to corrosion fissuring and pitting corrosion.     

Piping Cracks in JPDR, (IV)

Circumferential cracks detected in the JPDR (BWR) near welded joints connecting the nozzle safe-end to pipe (austenitic stainless steel) were studied in reference to the stresses applied in service, the conditions of welding, environment (O₂ and Cl^? concentration, water flow, temperature etc.), metallurgical structure and operating records, to determine the cause of cracking. Fatigue tests were also undertaken with simulated welded pipe of size to examine possible contribution of fatigue to the cracking.

The analysis indicated stress corrosion to be the principal cause of cracking, and that it had initiated in the heat-affected zone which had been sensitized by the excess heat input of welding. The factors contributing to the stress corrosion were the presence of oxygen in the fluid, which had at times attained a level exceeding 0.2 ppm, and which combined with stress, at times exceeding the yield strength. This had caused the cracks once initiated, to propagate along the grain boundary.     

Chloride induced stress corrosion cracking of candidate canister materials for dry storage of spent fuel

Susceptibility to chloride induced stress corrosion cracking (ESCC) of candidate canister materials, UNS S31260 and UNS S31254 stainless steels (SS), was investigated by a constant load test in air at temperatures of 343 and 353 K with relative humidity (RH) of 35%, and at 373 K without controlling RH. UNS S31260 and UNS S31254 SS did not fail until 37,700 h at 353 K with RH = 35%, where UNS S30403 SS failed within 250–500 h. The same tendency also was obtained at 343 K, suggesting the superior ESCC resistance of UNS S31260 and UNS S31254 SS. Even rust was not observed on the specimens tested at the temperature of 373 K. To explain the higher ESCC resistance, the pitting potential was measured in the saturated synthetic sea water at temperatures from 303 to 353 K, since ESCC is usually associated with localized corrosion such as pitting and may be closely related to the corrosion resistance. The pitting potentials of UNS S31260 and UNS S31254 SS were much higher than that of UNS S30403 SS. Thus, it was concluded that the superior ESCC resistance is attributable to the higher resistance of UNS S31260 and UNS S31254 SS to pitting corrosion. The critical relative humidity for ESCC, under which no ESCC occurs, is equal to or higher than 15% at temperatures < 353 K judging from ESCC behavior of UNS S30400 SS.     

Control of welding residual stress for ensuring integrity against fatigue and stress–corrosion cracking

The availability of several techniques for residual stress control is discussed in this paper. The effectiveness of these techniques in protecting from fatigue and stress–corrosion cracking is verified by numerical analysis and actual experiment. In-process control during welding for residual stress reduction is easier to apply than using post-weld treatment. As an example, control of the welding pass sequence for multi-pass welding is applied to cruciform joints and butt-joints with an X-shaped groove. However, residual stress improvement is confirmed for post-weld processes. Water jet peening is useful for obtaining a compressive residual stress on the surface, and the tolerance against both fatigue and stress–corrosion cracking is verified. Because cladding with a corrosion-resistant material is also effective for preventing stress–corrosion cracking from a metallurgical perspective, the residual stress at the interface of the base metal is carefully considered. The residual stress of the base metal near the clad edge is confirmed to be within the tolerance of crack generation. Controlling methods both during and after welding processes are found to be effective for ensuring the integrity of welded components.     

低锡Zr—4包壳管电子束焊接时发生的合金元素蒸发现象

采用电子探针的波谱分析方法,对国产低锡Ｚｒ－４包壳管的环焊缝试样进行表面成份分析。分析结果表明,从焊缝的外边到内边缘,Ｓｎ,Ｃｒ,Ｆｅ元素的化学成份在统计上呈增大趋势,腐蚀后出现了白色产物的试样表层,其Ｓｎ,Ｃｒ,Ｆｅ元素含量相当程度地降低。这一事实表明,国产低锡Ｚｒ－４包壳管采用电子束焊接时,在一定的焊接规范环焊缝的合金元素存在严重蒸发现象,特别是合金中锡元素的蒸发使其锡元素含量低于０．５％,导     

Cermet fuel in a light water reactor: a possible way to improve safety. Part II. Testing the fuel

This paper summarizes what is done for the experimental testing of cermet fuel with various matrix materials. Low neutron absorption, high heat conductivity, good corrosion resistance in water, low chemical interaction with cladding (zirconium alloy) and UO₂ in normal and accident conditions, technological ability — are the requirements of the matrix material [1]. Suitability of the proposed solutions to the cermet fuel design with respect to these requirements was proven through a series of experiments simulating fuel operating and accidental conditions.     

Compatibility of surface-coated steels, refractory metals and ceramics to high temperature lead–bismuth eutectic

Compatibility of cladding material with lead–bismuth eutectic at temperature higher than 650 °C is one of the most crucial issues for feasibility of lead–bismuth-cooled fast reactors with cycle efficiency as high as 40%. In order to search for corrosion-resistant materials with lead–bismuth eutectic at temperature higher than 650 °C, surface-coated steels, some refractory metals and various ceramics were tested by means of stirred-type corrosion test. Lead–bismuth was heated up to 700 °C electrically in an alumina crucible, and oxygen concentration in the lead–bismuth was adequately controlled by injection of argon, steam and hydrogen gas mixture into the lead–bismuth. Specimens of aluminum–iron-alloy-surface-coated steels, refractory metals and ceramics including SiC/SiC composites were immersed in the stirred lead–bismuth for 1000 h. It was found that the surface-coated steels showed good compatibility with the lead–bismuth due to formation of a thin and stable protection layer on the surfaces. Tungsten and molybdenum exhibited high corrosion resistance. On the other hand, niobium is not a reliable material for the high temperature LBE. SiC and Ti₃SiC₂ also exhibited high corrosion resistance. On the other hand, the physical performance of the SiC/SiC composite must be improved especially by minimizing the porosity.     

基于多物理场耦合的U3Si2燃料与双层SiC包壳组合的轻水堆燃料性能分析

基于COMSOL平台开发了一套基于多物理场全耦合的燃料性能分析程序,并通过径向功率分布模型对比验证了该程序的正确性与准确性;然后进一步分析了U₃Si₂燃料与双层SiC包壳组合、U₃Si₂燃料与锆合金包壳组合在反应堆正常运行工况下的性能,并与UO₂燃料与锆合金的组合进行了对比分析。计算结果发现U₃Si₂燃料与锆合金包壳组合相比UO₂燃料与锆合金的组合具有更低的燃料中心温度、裂变气体释放量及内压,但气隙闭合时间会提前;而U₃Si₂燃料与双层SiC包壳的组合相比U₃Si₂燃料与锆合金的组合具有更高的燃料中心温度、更大的裂变气体释放量及内压,且随着燃耗的增加,其燃料中心温度大幅增加,与锆合金包壳相比,双层SiC包壳能够有效延迟气隙闭合,缓解燃料与包壳的力学相互作用。      

Investigation of the Y<Subscript>2</Subscript>O<Subscript>3</Subscript> distribution in the weld joints of dispersion-hardened steel cladding of fast-reactor fuel elements

The results of investigations of the yttrium oxide distribution in the weld joints of dispersion-hardened steel cladding, manufactured by the powder metallurgy method, are presented. It is shown that when using the methods of fusing welding of thin-walled fuel-element cladding, the content and uniformity of the yttrium oxide distribution in the metal of a seam changes as compared with the cladding metal. The concentration and uniformity of the yttrium oxide distribution in the section of a weld joint obtained by pulsed laser welding is higher than that obtained with argon-arc welding. __________ Translated from Atomnaya énergiya, Vol. 102, No. 6, pp. 348–351, June, 2007.