Inconel690(TT)合金裂纹尖端小范围屈服时的腐蚀疲劳裂纹扩展行为研究

对Inconel 690(TT)合金腐蚀疲劳裂纹尖端塑性区微观结构进行观察,并研究裂纹尖端塑性区及载荷比对模拟压水堆环境下的裂纹扩展行为的影响。裂纹尖端小范围屈服时,模拟压水堆环境对裂纹扩展速率有3倍左右的加速作用。。     

某些加工因素对改性800合金碱性应力腐蚀破裂敏感性的影响

通过显微组织检验、拉伸试验、应力分析、C形环应力腐蚀试验、俄歇电子能谱(AES)分析、腐蚀形貌观察,研究了某些加工因素(冷加工和热处理)对国产改性800合金(800M)在沸腾的50%NaOH+0.3%SiO2+0.3%Na2S2O3溶液中的应力腐蚀破裂(SCC)敏感性的影响.冷加工拉伸25%的800M合金管的晶粒变形拉长,屈服强度和抗拉强度增大而延伸率降低,管的残余应力增加,SCC敏感性增加.对冷变形800M合金管热处理,随温度的升高,晶粒逐渐等轴化并变大,延伸率增大,屈服强度、抗拉强度和残余拉应力和SCC敏感性降低.AES分析表明,800M合金在沸腾碱液中恒电位极化后的表面膜是富Ni 而贫Fe 、Cr的.C形环试样碱性SCC裂纹在点蚀坑起源萌生,裂纹沿晶界扩展.     

Inconel690(TT)合金在压水堆二回路水环境下的腐蚀疲劳裂纹扩展行为研究

Inconel 690(TT)合金是压水反应堆蒸汽发生器传热管的关键材料之一,在压水反应堆工况下具有腐蚀疲劳开裂的风险。本文在裂纹尖端小范围屈服的条件下,研究了Inconel 690(TT)合金在模拟二回路水介质环境下的腐蚀疲劳裂纹扩展行为。研究发现:相对于室温情况下,模拟二回路水介质对疲劳裂纹扩展速率有最大3倍左右的加速作用;模拟二回水介质对疲劳裂纹扩展速率的加速作用受腐蚀疲劳裂纹非平面生长的影响,并与应力强度因子范围、最大应力强度因子及应力比密切相关。     

国产690合金与321不锈钢异种金属焊缝的应力腐蚀行为研究

利用慢应变速率试验,采用非标准的漏斗状试样,对国产690合金与321不锈钢异种金属焊接部位(包括690合金热影响区、焊缝、321不锈钢热影响区)在100 mg/L Cl~(-1)除O_2条件下和100 mg/L Cl~(-1)饱和O_2条件下的应力腐蚀行为进行研究。并通过慢应变速率应力-位移曲线和断口形貌对微观组织、氯离子、氧含量对于材料的应力腐蚀(SCC)的影响进行分析。结果表明:690合金热影响区在100 mg/L Cl~(-1)除O_2条件下不易发生SCC,在100 mg/L Cl~(-1)饱和O_2条件下表现出一定的SCC倾向;321不锈钢热影响区在2种条件下均表现出明显的SCC倾向;690合金热影响区的粗大晶粒不利于塑性变形的晶粒间相互协调,导致了热影响区SCC的倾向增大。     

冷变形316不锈钢在高温水中的应力腐蚀开裂行为

对不同冷变形量的核级316和316L不锈钢在高温水中的应力腐蚀开裂(SCC)行为进行了研究。通过试验,对溶解氧、氯离子和温度对裂纹扩展速率的影响进行了深入探讨和分析。试验结果显示,溶解氧和氯离子能明显加快材料的应力腐蚀开裂速率。当水化学条件一致时,325℃时的裂纹扩展速率较288℃时的裂纹扩展速率高。     

316LN在模拟压水堆一回路异常水化学条件下的应力腐蚀敏感性研究

采用慢应变速率拉伸试验（SSRT）法研究了氯离子(Cl^-)和溶解氧对316LN在模拟压水堆（PWR）一回路异常工况下的应力腐蚀开裂（SCC）的影响。结果表明：在饱和氧条件下,随着Cl^-浓度的增大,试样的延伸率降低,SCC敏感指数增大,当Cl^-浓度大于1 mg/L后开始萌生SCC裂纹;溶液除氧后,即使Cl^-浓度增大到10 mg/L也不会引发SCC裂纹。316LN的SCC裂纹萌生于表面的缺陷或贫Cr区,呈穿晶型向基体内扩展。     

X-750合金裂纹扩展速率的测量及SO_4~(2-)离子对裂纹扩展速率的影响

利用直流电压降方法(DCPD)测量X-750合金在空气中的疲劳开裂速率和高温高压水环境中的应力腐蚀裂纹扩展速率。介绍利用紧凑拉伸(CT)试样测量裂纹扩展速率的方法。基于滑移-氧化膜破裂-氧化模型,分析裂纹尖端特殊水化学环境形成的原理和过程,探讨水中溶解氧和SO42-离子在该环境形成过程中所起的作用。     

工质压力及蠕变对冷变形310S不锈钢在超临界水环境下的应力腐蚀开裂行为影响研究

310S不锈钢是一种性能较好的超临界水冷堆候选包壳材料,为丰富310S不锈钢在在超临界水环境下的应力腐蚀性能研究,特别是裂纹扩展速率方面的数据。本研究使用在线监测裂纹扩展的方法,测量了不同冷变形的310S不锈钢在多种工况下的裂纹扩展速率,分析了工质压力、高温蠕变等因素对310S开裂行为的作用。结果显示：超临界水或高温蒸汽的压力变化对310S不锈钢在500℃下的开裂行为的影响较为有限,冷变形作用促进材料的裂纹扩展,材料的高温蠕变行为在超临界水中对应力腐蚀开裂过程中具有较为重要的加速作用,特别是对于高冷变形和高载荷条件下的材料。本研究丰富了超临界水环境下310S的应力腐蚀裂纹扩展速率的数据,证明了提高材料的抗蠕变性能是优化包壳材料服役性能的重要手段之一,包壳设计制造的过程中应当避免较大幅度的冷变形。     

氢及氢化物对锆合金疲劳裂纹扩展速率的影响及估算

采用紧凑拉伸（CT）试样．研究了不同氢含量的Zr-4及Zr-Sn-Nb合金在室温下疲劳加载裂纹扩展（dα/dN）行为．用扫描电镜观察了断口形貌。结果表明，氢含量对疲劳裂纹扩展速率影响微弱，疲劳断裂受通常的裂纹萌生、稳态扩展和瞬间断裂机制控制。根据疲劳裂纹扩展机理．导出了裂纹扩展门槛值△Kth的关系式．得出了一个描述疲劳裂纹扩展速率油（dα/dN）与材料性能常数之间的关系式，该关系式可用于预测材料的疲劳裂纹扩展速率。用锆合金实验数据对（dα/dN）预测表达式进行验证．结果表明，预测值与实验值吻合较好。     

核蒸汽发生器用含Ti缓蚀添加剂高压釜暴露实验及表面分析

近来的研究表明，TiO2缓蚀添加剂能有效减缓蒸汽发生器传热管的应力腐蚀开裂(SCC)和晶间腐蚀(IGA)等局部腐蚀：本工作以不锈钢为试验材料，对含Ti缓蚀添加剂在高温浓碱环境中缓解应力腐蚀开裂的能力进行了初步的研究．高压釜暴露实验表明，在288℃、50％NaOH溶液中浸泡一周，含Ti缓蚀添加剂表现出较好的缓蚀效果。其中，锐钛矿、金红石型TiO2的作用要好于钛酸丁酯；但在相同环境下长时间(两周以上)浸泡，其抑制应力腐蚀开裂的能力并不显著，用扫描电镜(SEM)、X射线衍射(XRD)、X射线光电子能谱(XPS)等手段进行进一步的表面分析，研究了腐蚀产物形貌及结构，并探讨了合金在碱性环境中的去台金化趋势XPS纵深图谱表明锐钛矿型TiO2能明显抑制合金的去合金化趋势．防止裂纹沿贫Cr的晶界发展，从而起到缓解腐蚀的作用。     

IGSCC of grain boundary engineered 316L and 690 in supercritical water

This study evaluated the influence of a high fraction of special grain boundaries on the intergranular stress corrosion cracking susceptibility of 316L stainless steel and nickel base alloy 690 in supercritical water. By thermomechanically processing the alloys to create specimens with largely different special boundary fractions, it was possible to isolate the effects of the grain boundary structure on the intergranular stress corrosion cracking behavior. Constant extension rate tensile experiments were performed in 500 °C deaerated supercritical water, and SEM analysis of the cracking behavior was performed on the gage surfaces of the specimens. Results indicate that the fraction of cracked grain boundary length in the specimens with higher fractions of special boundaries is reduced for 316L and 690 by factors of 9 and 5 at 15% strain, and 3 and 2 at 25% strain, respectively. This reduction is due to the special boundaries, which at 25% strain have a frequency of cracking that is 9-18 times lower than that for a random high angle boundary.     

Role of Radiation-Induced Grain Boundary Segregation in Irradiation Assisted Stress Corrosion Cracking

Isolation of microstructural and microchemical effects on irradiation assisted stress corrosion cracking (IASCC) was attempted by means of low-dose high-temperature neutron irradiation in a material test reactor to get better understanding on IASCC. Microstructure, grain boundary segregation, hardness and SCC susceptibility were examined on stainless steels irradiated to 0.8 dpa at around 673 K. The irradiation caused well-developed grain boundary segregation without notable hardening or microstructural changes. No IASCC was found in 593 K hydrogenated water whereas the steels were highly susceptible to IASCC in 561 K oxygenated water. The results suggest that grain boundary segregation, probably Cr depletion, is sufficient to cause IASCC in oxygenated water and that other radiation-induced changes such as microstructure and hardening are required for IASCC in hydrogenated water.     

Effects of water chemistry and potential distribution on electrochemical corrosion potential measurements in 553 K pure water

The effects of water chemistry distribution on the potential of a reference electrode and of the potential distribution on the measured potential should be known qualitatively to obtain accurate electrochemical corrosion potential (ECP) data in BWRs. First, the effects of oxygen on a platinum reference electrode were studied in 553 K pure water containing dissolved hydrogen (DH) concentration of 26–105 μg kg^?1 (ppb). The platinum electrode worked in the same way as the theoretical hydrogen electrode under the condition that the molar ratio of DH to dissolved oxygen (DO) was more than 10 and that DO was less than 100 ppb. Second, the effects of potential distribution on the measured potential were studied by using the ECP measurement part without platinum deposition on the surfaces connected to another ECP measurement part with platinum deposition on the surfaces in 553 K pure water containing 100–130 ppb of DH or 100–130 ppb of DH plus 400 ppb of hydrogen peroxide. Measured potentials for each ECP measurement part were in good agreement with literature data for each surface condition. The lead wire connecting point did not affect the measured potential. Potential should be measured at the nearest point from the reference electrode in which case it will be not affected by either the potential distribution or the connection point of the lead wire in pure water.     

Advanced TEM characterization of stress corrosion cracking of Alloy 600 in pressurized water reactor primary water environment

Advanced transmission electron microscopy techniques were carried out in order to investigate stress corrosion cracking in Alloy 600 U-bend samples exposed in simulated PWR primary water at 330 °C. Using high-resolution imaging and fine-probe chemical analysis methods, ultrafine size oxides present inside cracks and intergranular attacks were nanoscale characterized. Results revealed predominance of Cr₂O₃ oxide and Ni-rich metal zones at the majority of encountered crack tip areas and at leading edge of intergranular attacks. However, NiO-structure oxide was predominant far from crack tip zones and within cracks propagating along twin boundaries and inside grains. These observations permit to suggest a mechanism for intergranular stress corrosion cracking of Alloy 600 in PWR primary water. Indeed, the results suggest that stress corrosion cracking is depending on chromium oxide growth in the grain boundary. Oxide growth seems to be dependent on oxygen diffusion in porous oxide and chromium diffusion in strained alloy and in grain boundary beyond crack tip. Strain could promote transport kinetic and oxide formation by increasing defaults rate like dislocations.     

Stress corrosion cracking on irradiated 316 stainless steel

Tests on irradiation-assisted stress corrosion cracking (IASCC) were carried out by using cold-worked (CW) 316 stainless steel (SS) in-core flux thimble tubes which were irradiated up to 5×10²⁶ n/m² (E>0.1 MeV) at 310°C in a Japanese PWR. Unirradiated thimble tube was also tested for comparison with irradiated tubes. Mechanical tests such as the tensile, hardness tests and metallographic observations were performed. The susceptibility to SCC was examined by the slow strain rate test (SSRT) under PWR primary water chemistry condition and compositional analysis on the grain boundary segregation was made. Significant changes in the mechanical properties due to irradiation such as a remarkable increase of strength and hardness, and a considerable reduction of elongation were seen. SSRT results revealed that the intergranular fracture ratio (%IGSCC) increased as dissolved hydrogen (DH) increased. In addition, SSRT results in argon gas atmosphere showed a small amount of intergranular cracking. The depletion of Fe, Cr, Mo and the enrichment of Ni and Si were observed in microchemical analyses on the grain boundary.     

Influence of Dissolved Hydrogen on Structure of Oxide Film on Alloy 600 Formed in Primary Water of Pressurized Water Reactors

In order to investigate the relationship between the susceptibility of primary water stress corrosion cracking (PWSCC) in Alloy 600 and the content of dissolved hydrogen (DH) in the primary water of pressurized water reactors (PWR), structural analysis of oxide films formed under four different DH conditions in simulated primary water of PWR was carried out using a grazing incidence X-ray diffractometer (GIXRD), a scanning electron microscope (SEM) and a transmission electron microscope (TEM). In particular, to perform accurate analysis of the thin oxide films, the synchrotron radiation of SPring-8 was used for GIXRD.

It has been observed that the oxide film is mainly composed of nickel oxide, under the condition without hydrogen. On the other hand, needle-like oxides are formed at 1.0 ppm of DH. In the environment of 2.75 ppm of DH, the oxide film has thin spinel structures. From these results and phase diagram consideration, the condition around 1.0 ppm of DH corresponds to the boundary between stable NiO and spinel oxides, and also to the peak range of PWSCC susceptibility. This suggests that the boundary between NiO and spinel oxides may affect the SCC susceptibility.     

Influence of oxide films on primary water stress corrosion cracking initiation of alloy 600

In the present study alloy 600 was tested in simulated pressurised water reactor (PWR) primary water, at 360 °C, under an hydrogen partial pressure of 30 kPa. These testing conditions correspond to the maximum sensitivity of alloy 600 to crack initiation. The resulting oxidised structures (corrosion scale and underlying metal) were characterised. A chromium rich oxide layer was revealed, the underlying metal being chromium depleted. In addition, analysis of the chemical composition of the metal close to the oxide scale had allowed to detect oxygen under the oxide scale and particularly in a triple grain boundary. Implication of such a finding on the crack initiation of alloy 600 is discussed. Significant diminution of the crack initiation time was observed for sample oxidised before stress corrosion tests. In view of these results, a mechanism for stress corrosion crack initiation of alloy 600 in PWR primary water was proposed.     

Mechanism of irradiation assisted stress corrosion crack initiation in thermally sensitized 304 stainless steel

Thermally sensitized 304 stainless steels, irradiated up to 1.2 × 10²¹ n/cm² (E > 1 MeV), were slow-strain-rate-tensile tested in 290 °C water containing 0.2 ppm dissolved oxygen (DO), followed by scanning and transmission electron microscopic examinations, to study mechanism of irradiation-assisted-stress-corrosion-crack (IASCC) initiation. Intergranular (IG) cracking behaviors changed at a border fluence (around 1 × 10²⁰ n/cm²), above which deformation twinning were predominant and deformation localization occurred earlier with increasing fluence. The crack initiation sites tended to link to the deformation bands, indicating that the crack initiation may be brought about by the deformation bands interacted with grain boundaries. Thus the border fluence is equivalent to the IASCC threshold fluence for the sensitized material, although the terminology of IASCC is originally given to the non-sensitized materials without microstructural definition. The IASCC threshold fluence was found to change with irradiation conditions. Changes in IASCC susceptibility and IASCC threshold fluence with fluence and DO were further discussed.     

Measurement of plastic strain of polycrystalline material by electron backscatter diffraction

It is important to know the degree of plastic strain in order to evaluate the susceptibility and crack growth rate of stress corrosion cracking (SCC) in stainless steel and nickel based alloy, because SCC is enhanced by the cold work and causes many problems in nuclear power plant components. In this study, electron backscatter diffraction in conjunction with scanning electron microscopy is applied to measure the plastic strain imposed to stainless steel by tensile load. A new parameter, which quantifies the spread of the crystal orientation within individual grains arising due to dislocation accumulation during plastic deformation, is correlated with imposed plastic strain. The new parameter is called ‘crystal deformation’ and is determined from the spread in misorientation from the central grain orientation. It is confirmed that this parameter has a good correlation with plastic strain and is not affected by the data density of the crystal orientation map. The dislocation density distribution is also evaluated from the misorientation from the central orientation. Relatively high dislocation density was observed near grain boundaries and grain boundary triple points, which was consistent with the observed deterioration of EBSD pattern quality in those locations.     

Effects of the microstructure and alloying elements on the iodine-induced stress-corrosion cracking behavior of nuclear fuel claddings

A quantitative analysis of the iodine-induced stress-corrosion cracking (ISCC) process for a Zircaloy-4 cladding and a ZIRLO cladding was performed to support grain-boundary pitting coalescence (GBPC) and pitting-assisted slip cleavage (PASC) models for an ISCC behavior. It was focused on the effects of the microstructure on a grain-boundary pitting and the transgranular cracking phenomenon during a crack propagation step. Also, a microscopic analysis of the stress intensity applied to pits on a grain surface was performed to evaluate the cleavage crack propagation rate of the stress-relieved (SR) and re-crystallized (RX) grains. During the ISCC cracking, it was revealed that the grain shape and cleavage habit plane played important roles in a grain cracking, which resulted in an IG–TG_c (TG cracking by cleavage) or a TG_f (TG cracking by fluting)–TG_c cracking mode. An IG–TG_c cracking took place for the RX microstructure through a GB pitting, however, a TG_f–TG_c cracking did occur for the SR one which in turn increased its propagation rate. The increase of the pitting resistance at the grain-boundary played a critical role in the crack propagation rate of the ZIRLO cladding.