基于蠕变孔洞长大理论的高温构件蠕变强度设计准则研究

在分析高温构件蠕变失效微观机理的基础上,提出了基于孔洞长大理论的蠕变应变设计准则和蠕变应力设计准则.定义了蠕变等效应力和蠕变等效应变,探讨了蠕变许用应力和蠕变许用应变的确定原则.这些设计准则考虑了蠕变失效的微观机理和时间相关性的影响,能给出比传统设计方法更为稳定和合理的设计结果.分析了在蠕变强度设计上存在的困难,并提出了相应的建议.     

国产反应堆压力容器用16MND5钢的蠕变损伤本构模型研究

为了获得反应堆压力容器（RPV）材料在高温下的蠕变行为,保证RPV在严重事故工况下的完整性,本研究对国产RPV用16MND5钢的高温蠕变性能进行了测试,获得了600~900℃下材料的蠕变性能,并基于应变强化的基本蠕变本构模型与基于延性耗竭理论的蠕变损伤模型,建立了适用于16MND5钢的蠕变损伤本构模型,给出了材料的蠕变损伤模型参数。结果表明,本文提出的蠕变损伤本构模型的有限元模拟数据与试验数据符合性较好,验证了此蠕变损伤模型的正确性。该方法可用于严重事故情况下RPV的蠕变损伤分析,为RPV的完整性分析提供支持。      

基于损伤力学的TMSR-LF1堆容器接管非弹性蠕变损伤分析

钍基熔盐液态实验堆(Thorium Molten Salt Reactor-Liquid Fuel 1,TMSR-LF1)反应堆压力容器(简称"堆容器")长期在650°C的高温下服役,对其进行蠕变损伤分析至关重要。本文旨在采用非弹性分析方法进行TMSR-LF1堆容器接管的蠕变损伤计算与评估。基于损伤力学理论,通过拟合650°C下UNS N10003合金的蠕变试验数据,得到了Lemaitre多轴蠕变损伤模型的材料常数。蠕变断裂寿命的理论预测值与试验结果基本吻合,最大误差7.38%。然后通过有限元分析,得到了TMSR-LF1堆容器接管正常运行工况下的等效应力,并根据Lemaitre多轴蠕变损伤模型得到了非弹性蠕变损伤值。计算结果表明:TMSR-LF1堆容器接管在10年寿期内的最大蠕变损伤约0.082,满足限值要求。     

假想堆芯熔化严重事故下反应堆压力容器完整性的研究进展与建议

堆芯熔化严重事故下保证反应堆压力容器完整性非常重要,高温蠕变失效是堆芯熔化严重事故下反应堆压力容器的主要失效模式。本文介绍了近年来在假想堆芯熔化严重事故下国内外反应堆压力容器高温蠕变行为的研究进展及现状,着重阐述了在材料高温蠕变试验、缩比模型试验和数值模拟等方面取得的成果,以及国内在RPV结构完整性高温蠕变行为研究方面的最新成果,指出了目前研究中存在的问题并提出开展多轴拉伸试验、三维耦合效应的温度场分析和缩比模型试验等研究方向。     

TMSR-LF1停堆系统高温螺栓连接结构应力松弛分析与结构安全评定

钍基熔盐液态堆(Thorium Molten Salt Reactor-Liquid Fuel 1,TMSR-LF1)停堆系统螺栓连接结构服役环境约在650°C的高温区域,连接结构包括三种材质的构件;升温过程热膨胀以及高温下寿期内的蠕变效应,对螺栓的预紧力都有很大影响。本文采用ANSYS程序,对TMSR-LF1停堆系统高温螺栓连接结构,在预紧载荷及热膨胀组合作用下的结构进行了应力分析和寿期内蠕变应力松弛分析。考虑从常温升高至工作温度的过程中,连接结构件由于使用不同材料,其热膨胀差导致预紧力发生变化的过程;着重研究分析运行寿期内螺栓结构材料的高温蠕变,所引起应力松弛的变化规律,及其对螺栓连接结构预紧力的影响;并根据ASME-III-5-HBB规范对螺栓进行力学分析和应力评定,论证该螺栓连接件全寿期内结构安全可靠。     

基于蠕变的高温构件应力松弛损伤模型

基于SchIottner-Seeley平均蠕变断裂速率原理和松弛方程,构建了应力松弛损伤模型;采用该模型对高温紧固材料1Cr10NilMoW2VNbN进行了损伤预测和实验验证.结果表明,该模型预测的数据与实际试验结果吻合较好.     

304不锈钢高温非比例多轴应变循环变形行为研究

为了对材料的高温应变循环变形行为进行精确的本构描述,在350℃和700℃下,对304不锈钢在不同加载路径下的单轴和非比例多轴应变循环变形行为进行了实验研究.讨论了材料在不同加载路径及不同工况下的循环硬化特性.研究表明:304不锈钢的高温非比例多轴应变循环变形行为具有明显的温度依赖性和路径依赖性.研究结果为后续循环本构模型的建立提供了实验基础.     

304不锈钢非比例多轴时间相关棘轮行为的本构模型研究

基于304不锈钢在不同加载速率和不同保持时间下得到的非比例多轴时相关棘轮行为的实验研究结果,在Abdel-Karim-Ohno模型的基础上,建立了一个非比例多轴时间相关循环本构模型.该模型通过在背应力演化律中引入与非比例度相关的静力恢复项,在各向同性硬化律中引入Tanaka非比例度来考虑非比例路径对时间相关棘轮行为的影响.模拟结果与实验结果的比较表明:该本构模型对室温和高温下多轴时间相关棘轮行为的演化规律均能给予较合理的描述.     

氩气保护条件下微小试样的高温蠕变行为研究

高温蠕变性能是反应堆材料性能评价的一个重要指标,为降低试验成本、辐射剂量及加强辐照试验的穿透度,用非常规微小试样已成为试验研究的趋势。用微小片状试样进行高温蠕变试验。为避免高温氧化对材料性能数据的影响,用自主设计改进的带氩气保护装置的高温蠕变机,研究超临界水堆包壳候选材料镍基合金C276在氩气保护条件下的高温蠕变行为。根据实验数据得到不同应力水平下的高温蠕变曲线,分析蠕变机理,评价材料的蠕变性能。     

锆合金辐照蠕变和生长的宏介观模型研究进展

锆合金作为核反应堆堆芯的主要结构材料之一,在服役过程中会发生辐照蠕变和生长行为,严重影响其使用可靠性.预测锆合金的辐照蠕变和生长是保障反应堆安全运行的关键.本文聚焦于两类锆合金构件,包括压水堆用锆合金包壳管及重水堆用Zr-2.5Nb压力管,分别从宏介观尺度详细综述了其辐照变形预测模型.针对适用于包壳管的宏观经验模型及介...     

Coupled thermal structural analysis of LWR vessel creep failure experiments

Considering the hypothetical core melt down scenario for a light water reactor (LWR) the failure mode of the reactor pressure vessel (RPV) has to be investigated to determine the loadings on the containment. The failure of reactor vessel retention (FOREVER)-experiments, currently underway, are simulating the thermal and pressure loadings on the lower head for a melt pool with internal heat sources. Due to the multi-axial creep deformation of the vessel with a non-uniform temperature field these experiments are an excellent source of data for validation of numerical creep models. Therefore, a finite element (FE) model has been developed based on a commercial multi-purpose code. Using the computational fluid dynamics (CFD) module the temperature field within the vessel wall is evaluated. The transient structural mechanical calculations are performed using a new numerical approach, which avoids the use of a single creep law employing constants derived from the data for a limited stress and temperature range. Instead of this a three-dimensional array is developed where the creep strain rate is evaluated according to the values of the actual total strain, temperature and equivalent stress. Care has to be exercised performing post-test calculations particularly in the comparisons of the measured data and the numerical results. Considering the experiment FOREVER-C2, for example, the recorded creep process appears to be tertiary, if a constant temperature field is assumed. But, small temperature increase during the creep deformation stage could also explain the observed creep behavior. Such considerations provide insight and better predictive capability for the vessel creep behavior during prototypic severe accident scenarios.     

The effect of random temperature fluctuations on creep and creep rupture of cylindrical tubes

The design of LMFBR plants requires extensive creep analysis, since many in-core structures and primary system components operate at elevated temperatures. In the design process, exact information on the temperature field is often lacking and this, together with the temperature sensitivity of creep phenomena, leads to uncertainties in derived quantities such as strain and total deformation. This study considers the qualitative and quantitative implications of random temperature data by deriving expressions for the expectation value and variance of quantities such as displacement and stress in creep of thin, pressurized tubes. Also, a nondeterministic analog of an existing theory of creep rupture is employed to study the impact of random temperature fluctuations on time to brittle and ductile rupture. Data for stainless steel are applied in various numerical examples and these, together with analytical considerations, are used to formulate qualitative generalizations of importance to the design process.     

Crack growth determination on laboratory components

The present work outlines the reasoning behind the selection of laboratory component tests for the validation of design and remanent life models governing crack growth behaviour. For the case of creep crack growth a ferritic and an austenitic alloy have been studied and a reference stress based solution used to successfully relate the stress rupture behaviour of internally and externally, axially and circumferentially notched, tubular components to base line creep data. Using the same reference stress based approach, it has been demonstrated that the notched component creep crack growth rates exhibit the same C^* dependence as conventional compact tension specimens. For 316L stainless steel components subjected to thermal fatigue conditions simulative of the fusion reactor first wall, a modified version of the superposition method of Buchalet and Bamford has been applied to estimate the stress intensity range as a function of crack length during the test. By this approach the crack growth rate dependency on stress intensity range for a variety of notch geometries is seen to be broadly in line with the conventional specimen mechanical fatigue data. Recent studies of crack growth under combined creep and thermal fatigue conditions are described and some early results are reported.     

Uncertainties of creep model in stress analysis and life prediction of graphite component

The irradiation-induced creep is a key factor in stress analysis and life prediction of nuclear graphite in high temperature gas-cooled reactors (HTRs). Numerous creep models have been established and good agreements have been observed with uni-axial creep experiments. However, the effect of creep strain ratio has not been fully addressed, and the primary creep strain is considered in some cases less important in comparison with the secondary one. These uncertainties in creep model might result in large discrepancies in the evaluation of stresses and service lives of graphite components. In this paper, the variation of creep strain ratio and the impact of the primary creep strain are studied numerically and the corresponding discrepancies in stresses and life prediction of graphite components in HTRs are discussed. Two implicit formulations of the incremental finite element solution for the parameter variations of creep models are presented and integrated into a finite element code developed by INET. The numerical results show that both increase of the creep strain ratio and absence of the primary creep strain will lead to an increase of stress levels and decrease of service life dramatically, suggesting that uncertainties of creep models have to be taken into account in the design of graphite components in HTRs.     

Estimation of crack growth in the creep range during plastic cyclic loading

Crack growth investigations were performed on the creep-resistant steel 13 CrMo 4 4 in the fatigue and the creep fatigue regime, especially regarding the influence of creep damage on crack growth. To this effect, 2% creep strain was applied to the material at a temperature of 560°C. The crack propagation rate was determined as a function of the specimen shape, temperature, test frequency and hold times. In the case of compact tension (CT-)specimens, creep pretreatment does not affect crack growth. For center-cracked tension (CCT-)specimens, however, the creep pretreatment results in a considerable increase in the crack propagation rate. Hold times of 90 minutes at maximum loading cause an increase in da/dN due to further cavity nucleation. The hold time at which cavity nucleation might occur is evaluated. The dependency on frequency of crack growth may be evaluated by means of a linear superposition of creep and fatigue crack growth. The transition frequency above which pure fatigue crack growth occurs is calculated and the regimes of fatigue, creep and creep—fatigue interaction with environmental influences are characterized.     

The development of validation methodology of multi-axial creep damage constitutive equations and its application to 0.5Cr0.5Mo0.25V ferritic steel at 590 °C

Research progress on the development of validation methodology for multi-axial creep damage constitutive equations and its specific application to 0.5Cr0.5Mo0.25V ferritic steel at 590 °C is presented. A set of new phenomenological multi-axial creep damage constitutive equations was proposed aiming at overcoming the deficiency of inconsistency between predicted rupture strains and observed ones. Based on these explicit consistent requirements, an improved validation methodology is proposed and applied to 0.5Cr0.5Mo0.25V ferritic steel at 590 °C. It shows that the predictions of this new set of constitutive equations are consistent with experimental observations. It also reveals a significant difference in creep curves between different sets of constitutive equations and the need for experimental data so that the coupling of damage and creep deformation can be further examined.     

The various creep models for irradiation behavior of nuclear graphite

Graphite is a widely used material in nuclear reactors, especially in high temperature gascooled reactors (HTRs), in which it plays three main roles: moderator, reflector and structure material. Irradiation-induced creep has a significant impact on the behavior of nuclear graphite as graphite is used in high temperature and neutron irradiation environments. Thus the creep coefficient becomes a key factor in stress analysis and lifetime prediction of nuclear graphite. Numerous creep models have been established, including the visco-elastic model, UK model, and Kennedy model. A Fortran code based on user subroutines of MSC.MARC was developed in INET in order to perform three-dimensional finite element analysis of irradiation behavior of the graphite components for HTRs in 2008, and the creep model used is for the visco-elastic model only. Recently the code has been updated and can be applied to two other models—the UK model and the Kennedy model. In the present study, all three models were used for calculations in the temperature range of 280–450 °C and the results are contrasted. The associated constitutive law for the simulation of irradiated graphite covering properties, dimensional changes, and creep is also briefly reviewed in this paper. It is shown that the trends of stresses and life prediction of the three models are the same, but in most cases the Kennedy model gives the most conservative results while the UK model gives the least conservative results. Additionally, the influence of the creep strain ratio is limited, while the absence of primary creep strain leads to a great increase of failure probability.     

Elevated temperature creep crack growth: State-of-the-art review and recommendations

Presented in this paper is a detailed literature review of the emerging technology of creep crack growth. The application of this technology is directed at components which must withstand thermo-mechanical loads in high temperature range. Examples are components of breeder reactor systems and turbine disk alloys for aerospace applications. Component failures due to creep crack growth have been reported to occur in heat-affected zones and in defective welds. However, current design codes (such as ASME) do not permit crack-like defects in creep range.The essential feature of creep is that it is a thermally activated process involving significant time-dependent plastic and creep deformations. Much effort in the past decade has been directed toward experimentally identifying the parameters that would govern crack growth under creep conditions. However, no completely successful single parameter has emerged.The review is divided into a discussion of the basic creep deformation mechanisms, experimental crack growth correlations, analytical predictions, and numerical computations. Greater emphasis is given to describing the developments in the past five years. Finally, a combined numerical and experimental program is recommended for further research in this area. An alternate strategy to select pertinent experimental data from the published literature and to use them to conduct numerical/analytical work is also suggested, which would be much more economical to pursue.