硅对低活化马氏体钢电子辐照行为的影响

利用超高压透射电子显微镜研究了两种成分的低活化马氏体钢(CLAM钢)的辐照损伤行为。结果表明：电子辐照能在未添加硅的CLAM钢中产生辐照空洞;在450℃下辐照至14dpa时,空洞数密度约为8.7×10²¹m^－3,辐照肿胀率约为0.26％;在450℃下的辐照肿胀率明显比500℃下的高;当损伤率为2×10^－3dpa/s时,添加合金元素硅能显著提高CLAM钢的抗辐照肿胀能力,未在添加硅的CLAM钢中实验观察到辐照空洞的形成。在450℃下进行辐照时,添加硅的CLAM钢出现明显的辐照共格析出现象。     

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。     

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.     

中国低活化马氏体钢室温和150℃下1/2CT断裂韧性实验研究

利用卸载柔度法参考ASTM E1820-11标准对聚变堆候选结构材料中国低活化马氏体(CLAM)钢在室温和1 50℃条件下的断裂韧性进行了测试分析,同时对断面进行了扫描电子显微镜(SEM)微观分析。结果显示,CLAM钢1/2CT样品在室温和1 50℃条件下测试的断裂韧性J_Q分别为287 kJ/m~2和256 kJ/m~2,在这两个测试温度下CLAM钢均表现出较高的断裂韧性,且随着测试温度的升高断裂韧性有所降低。断面SEM观察显示韧窝布满整个断面,裂纹稳定扩展区域为韧性断裂。     

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。     

钇对9Cr-2WVTa低活化马氏体钢力学性能的影响

研究了稀土合金元素钇对聚变堆用低活化马氏体钢9Cr-2WVTa力学性能的影响,分析了钇在低活化马氏体钢中的冶金行为.研究结果表明,钇元素容易在钢中聚集形成富钇的块状夹杂,割裂了基体的连续性,容易破裂形成微孔;轧板中这些富钇块夹杂沿着轧制方向成条线状分布,使得在拉伸和冲击断裂时出现断口分层现象,降低了钢的力学性能.     

中国低活化马氏体钢CLAM在液态锂铅中腐蚀的初步实验研究

液态金属锂铅包层是最具发展潜力的聚变堆包层之一,其首选结构材料为低活化铁素体/马氏体钢,而它与液态锂铅的相容性是聚变堆材料研究领域的关键问题之一.本文介绍中国低活化马氏体钢CLAM在液态金属锂铅回路DRAGON-1热对流工况下的实验情况及500 h 480 ℃下初步腐蚀实验结果,并与同样工况下316L奥氏体钢腐蚀结果进行了对比分析.结果显示CLAM钢与液态锂铅的相容性优于316L钢.     

CLAM-316L TIG焊接接头显微组织特征分析

采用309焊丝对中国低活化马氏体(CLAM)钢和316L不锈钢进行TIG焊,并利用光学显微镜、扫描电镜和维氏硬度仪分析对接接头的微观组织和显微硬度分布。结果表明,CLAM-316L TIG焊接头按照显微组织特征可分为六个区域,即CLAM钢母材、CLAM钢热影响区、CLAM钢熔合区、焊缝金属、316L热影响区、316L母材。CLAM钢熔合区显微组织为淬火马氏体;焊缝金属区为粗大的胞状枝晶组织;316L热影响区和母材均为奥氏体组织,热影响区晶粒尺寸有明显长大。焊态接头整体硬度分布均匀,只有CLAM钢熔合区硬度较高。     

中国低活化马氏体钢CLAM研究进展

低活化铁素体/马氏体钢(RAFM钢)被普遍认为是未来聚变示范堆和聚变动力堆的首选结构材料。国际上给予了高度重视,许多国家都在研发其特有的RAFM钢。中科院等离子体物理研究所在与国内外多家单位的合作下发展了中国低活化马氏体钢———CLAM。本文总结了CLAM钢研制发展的主要进展,包括其成分优化设计、冶炼加工制备工艺、物理性能、机械性能、辐照性能及与液态LiPb的相容性等测试与研究以及各种焊接工艺研究等,并对今后的发展方向进行了展望。     

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。     

Temperature effects on the mechanical properties of candidate SNS target container materials after proton and neutron irradiation

This report presents the tensile properties of EC316LN austenitic stainless steel and 9Cr-2WVTa ferritic/martensitic steel after 800 MeV proton and spallation neutron irradiation to doses in the range 0.54-2.53 dpa at 30-100 °C. Tensile testing was performed at room temperature (20 °C) and 164 °C. The EC316LN stainless steel maintained notable strain-hardening capability after irradiation, while the 9Cr-2WVTa ferritic/martensitic steel posted negative hardening in the engineering stress-strain curves. In the EC316LN stainless steel, increasing the test temperature from 20 to 164 °C decreased the strength by 13-18% and the ductility by 8-36%. The effect of test temperature for the 9Cr-2WVTa ferritic/martensitic steel was less significant than for the EC316LN stainless steel. In addition, strain-hardening behaviors were analyzed for EC316LN and 316L stainless steels. The strain-hardening rate of the 316 stainless steels was largely dependent on test temperature. A calculation using reduction of area measurements and stress-strain data predicted positive strain hardening during plastic instability.     

9Cr3W低活性马氏体钢微观组织及力学性能的初步研究

通过提高W含量，调整V、Ta、Ti、N等微合金元素含量，设计了9Cr3W型低活性马氏体钢。研究了该钢的微观组织结构与硬化、时效及相转变行为，对其进行了拉伸性能和冲击韧性测试。与Eurofer97钢相比，该钢表现出优良的高温拉伸性能。分析了9Cr3W钢用作超临界水堆堆芯内部件及包壳材料的可行性，其高温力学性能远优于Zr合金包壳材料;拉伸性能与T91钢相当，且韧脆转变温度低于T91钢，冲击吸收功上限高于T91钢，具有优良的冲击韧性;9Cr3W钢的高温瞬时强度低于奥氏体316不锈钢，成为制约其用于超临界水堆堆芯内部件及包壳的因素之一。     

Si含量对9%Cr铁素体马氏体钢微观结构和力学性能的影响

铁素体马氏体（F/M）钢是铅冷快堆堆芯的主要候选材料之一,提高Si含量可提高其抗腐蚀性能,但影响其微观结构和力学性能。为研发兼顾力学性能和抗腐蚀性能的高Si含量F/M钢,本文对Si含量（质量分数为034%、061%、080%、098%和120%）对9%Cr F/M钢微观结构和力学性能的影响进行了研究。结果显示,室温下通过正火（1 050 ℃,05 h,空冷）+回火（760 ℃,15 h,空冷）热处理制备的F/M钢均为全马氏体组织。钢的屈服强度和抗拉强度均随Si含量的增加而增加。Si含量对钢的组织及冲击性能的影响可分为两个阶段,当F/M钢中Si含量为034%~080%时,其组织、冲击性能变化很小;Si含量为098%~120%时,F/M钢中的第二相尺寸、数量增加,沿马氏体板条界面析出少量的Laves相,F/M钢的冲击韧性降低。本研究9%Cr F/M钢中Si元素的最优添加量应低于08%,使钢在保持较高强度的同时兼具良好的韧性。     

Effects of Fast Reactor Irradiation Conditions on Tensile and Transient Burst Properties of Ferritic/Martensitic Steel Claddings

The effects of fast neutron irradiation conditions have been investigated by focusing on the mechanical properties of 11Cr-0.5Mo-2W, Nb, V ferritic/martensitic (F/M) stainless steel (PNC-FMS) and 10.5Cr-1.5Mo, Nb, V F/M stainless steel (HT9M) claddings, especially tensile and transient burst properties. These two F/M claddings were irradiated at temperatures from 693 to 833K to 42.5 dpa (displacement per atom) in the experimental fast reactor JOYO using the PFB090 fuel test subassembly. Post-irradiation tensile and temperature-transient-to-burst tests were carried out for defueled cladding specimens. The results of mechanical tests for the PNC-FMS cladding showed that there was no significant degradation in tensile and transient burst strengths even after fast neutron irradiation. On the other hand, the strength of the HT9M cladding tended to shift to lower values than those of as-received specimens. The differences in tensile and transient burst strengths between the two claddings were attributed to martensite structural stability which was related to the stable solid solution elements.     

Development of 9Cr-ODS Martensitic Steel Claddings for Fuel Pins by means of Ferrite to Austenite Phase Transformation

For use as fuel cladding of liquid metal fast reactors, Fe-0.12C-9Cr-2W ODS martensitic steel claddings were developed by cold-rolling under the softened ferrite phase induced by slow cooling from austenite phase, subsequently by ferrite to austenite phase transformation to break up substantially elongated grains produced by cold-rolling at the final heat-treatment. The produced claddings showed noticeable improvement in tensile and creep rupture strength that are considerably superior to PNC-FMS and even austenitic PNC316 at higher temperature and extended time to rupture. The strength improvement is mainly attributed to titanium addition in ODS martensitic steels through its reduction of Y₂O₃ particle size and shortening inter-particles spacing. The behavior of oxide particle size reduction is associated with stoichiometry between Y₂O₃ and TiO₂.     

反应堆内17-4PH马氏体不锈钢阀杆材料长时间服役后的热老化脆化行为与断裂机制

核电站主蒸汽系统中的阀杆等关键部件常用材料为17-4PH马氏体不锈钢，在300 ℃左右的高温环境下，该材料会随服役时间的延长发生热老化脆化，具体表现为韧脆转变温度（DBTT）升高、上平台能量降低和硬度增加，对反应堆的安全运行构成潜在威胁。本文针对热老化后的17-4PH马氏体不锈钢阀杆材料，通过扫描电子显微镜（SEM）、电子背散射衍射（EBSD）等微观分析手段，研究其热老化脆化行为和断裂机制。结果表明，17-4PH马氏体不锈钢热老化后，马氏体板条束长大，晶界总数增多，冲击断口上微裂纹数量增多，且尺寸近似于马氏体板条束尺寸。结合其冲击性能等进一步分析了材料的脆性断裂机制，结果显示，小角度晶界与Cu相互作用产生的硬化导致脆化，是17-4PH马氏体不锈钢发生热老化脆化的主要原因。     

Sodium effects on mechanical performance and consideration in high temperature structural design for advanced reactors

Sodium environmental effects are key limiting factors in the high temperature structural design of advanced sodium-cooled reactors. A guideline is needed to incorporate environmental effects in the ASME design rules to improve the performance reliability over long operating times. This paper summarizes the influence of sodium exposure on mechanical performance of selected austenitic stainless and ferritic/martensitic steels. Focus is on Type 316SS and mod.9Cr-1Mo. The sodium effects were evaluated by comparing the mechanical properties data in air and sodium. Carburization and decarburization were found to be the key factors that determine the tensile and creep properties of the steels. A beneficial effect of sodium exposure on fatigue life was observed under fully reversed cyclic loading in both austenitic stainless steels and ferritic/martensitic steels. However, when hold time was applied during cyclic loading, the fatigue life was significantly reduced. Based on the mechanical performance of the steels in sodium, consideration of sodium effects in high temperature structural design of advanced fast reactors is discussed.     

低活化马氏体钢限制性模压织构演化行为及力学性能研究

利用低活化马氏体钢在500、600 ℃下进行了多道次限制性模压(CGP)实验,研究了不同温度下变形道次对其显微组织和力学性能的影响。结果表明：经3道次CGP变形后,低活化马氏体钢的平均晶粒尺寸从初始回火态的1.37 μm细化到0.88 μm;马氏体中形成了明显的（121）［012］、（011）［111］、（101）［111］织构,同时有（213）［111］织构出现,{112}{111}面织构的出现有效提升了材料的拉伸性能;铁素体中出现（012）［021］织构和明显的{013}〈113〉织构;抗拉强度与硬度显著上升,延伸率小幅降低。500 ℃下,抗拉强度经过1道次CGP变形后从初始态的586.31 MPa提升至693.01 MPa,3道次后又略下降至689.74 MPa;延伸率从初始态的18.59%降至12.13%。600 ℃下,抗拉强度经过1道次CGP变形后提升至685.97 MPa,3道次CGP变形后又略下降至679.30 MPa;延伸率降至15.62%。上述结果证明,CGP变形是提升低活化钢板力学性能的有效方法之一。