辐照损伤对锆合金电化学性能的影响

综述了堆内辐照对锆合金电化学性能影响的概况，浅析了堆内辐照损伤的机理，并重点探讨了主要的堆内辐照源——中子辐照对锆合金微观结构与氧化性能的影响。进一步阐述了堆外离子轰击模拟堆内中子辐照研究方法的进展概况，并就离子轰击实验参量的选择进行了较为深入的分析。     

对堆芯熔化条件下锆合金包壳腐蚀动力学有关问题的讨论

针对在堆芯熔化条件下建立铝合金包壳腐蚀动力学模型时所涉及的有关问题和已有的模型进行了讨论和评述。     

N18锆合金的单轴拉伸和应力松弛性能

本工作试验研究20~700℃、不同应变加载速率下N18锆合金的单轴拉伸和应力松弛性能。结果表明,N18合金的单轴拉伸应力-应变曲线出现明显的屈服拐点,且温度低于500℃时呈现后继屈服强化,高于500℃后又呈后继屈服软化。除横向试样的断面收缩率高于轧向试样外,试样取向对N18合金的单轴性能影响不大。温度低于300℃时,N18合金的应变速率敏感性受温度的影响不大;350℃时,N18合金的敏感系数达到最小值,其后,对应变速率的敏感性随着温度的升高逐渐增强。N18合金在不同温度和应变水平下均产生明显的应力松弛。在300℃以内,最大应力松弛程度受温度影响较小,且随应变水平的增大明显降低;在350~550℃范围内,应变水平越高,对应的最大应力松弛程度越大;N18合金的最大松弛程度在350℃附近出现最小值。在350~450℃范围内,N18合金表现出明显的动态应变时效特性。     

Influence of Hydride Re-orientation on BWR Cladding Rupture under Accidental Conditions

Hydride precipitation along the radial-axial plane increases in high burn-up boiling water reactor (BWR) fuel claddings. The radially-oriented hydrides may have an important role during fuel behavior in a reactivity-initiated accident and may reduce ductility of the cladding under pellet-cladding mechanical interaction (PCMI) conditions. In order to promote a better understanding of the influence of the radial hydrides on cladding failure behavior under the PCMI conditions, tube burst tests were conducted for unirradiated BWR claddings charged with 200 to 650 ppm of hydrogen. About 20 to 30% of hydrides were re-oriented and precipitated along the radial-axial plane. The claddings exhibited large rupture openings with an axial crack at room temperature and 373 K. The crack penetrated through cladding wall preferentially along the radial hydrides, and radial cross section showed cladding failure in a brittle manner. However, reduction in residual hoop strain by precipitation of the radial hydrides was very small. It is accordingly expected that ductility of high burn-up BWR cladding is significantly reduced not only by precipitation of radial hydrides as far as hydrogen concentration and radial hydride fraction range in the present study.     

Thresholds for failure of high-burnup LWR fuels by Pellet Cladding mechanical interaction under reactivity-initiated accident conditions

ABSTRACT

To contribute to the future updating on the Japanese safety criteria for pellet/cladding mechanical interaction (PCMI) failure of light water reactor fuels under reactivity-initiated accident (RIA) conditions, this paper summarizes the recent important outcomes from research programs with the Nuclear Safety Research Reactor (NSRR). Applicability of current criteria, which are defined as a function of fuel burnup and possibility of introducing another parameter for new criteria were evaluated based on the results of the RIA-simulated pulse irradiation tests, post-test examinations, and supporting analytical work, such as the reevaluation of fuel enthalpies in earlier NSRR experiments. Failure-threshold curves based on cladding hydrogen content as a primary measure of fuel degradation have been proposed as a possible alternative that can be used to judge the occurrence of PCMI failure to ensure conservativeness in a more pertinent manner.     

锆合金与不锈钢的连接技术

分析了核反应堆用锆合金与不锈钢主要连接技术的研究结果及存在的问题。普通熔化焊接方法会导致大量脆性金属间化合物的出现，机械连接方法产生的应力过高，因而这2种方法均不可行。其他几种连接方法各有优缺点。     

锆合金管材氢化物生长方式的研究

研究了锆金管材中氢化物的生长方式。结果表明：氢化物片（条）是在晶界上生长,并且以尖端延伸的方式向前发展。氢化物片的厚度近似一常数值,与氢含量（渗氢量）没有对应关系。氢含量的增加只增加化物片的数量。同时分析了造成氢化物这种生长方式的原因。     

Zr—4合金单调和循环变形结构的扫描电镜原位观察

利用ＳＥＭ原位观察了Ｚｒ－４合金单调和循环变形过程中,试样表面滑移,裂纹萌生及扩展特征。结果表明：拉伸过程中,随着外应力增大,滑移程度加剧,从单滑移逐渐向多滑移转化;     

Prediction of water droplet evaporation on zircaloy surface

In the present experimental study, the prediction of water droplet evaporation on a zircaloy surface was investigated using various initial droplet sizes. To the best of our knowledge, this may be the first valuable effort for understanding the details of water droplet evaporation on a zircaloy surface. The initial contact diameters of the water droplets tested ranged from 1.76 to 3.41 mm. The behavior (i.e., time-dependent droplet volume, contact angle, droplet height, and contact diameter) and mode-transition time of the water droplet evaporation were strongly influenced by the initial droplet size. Using the normalized contact angle (θ*) and contact diameter (d*), the transitions between evaporation modes were successfully expressed by a single curve, and their criteria were proposed. To predict the temporal droplet volume change and evaporation rate, the range of θ* > 0.25 and d* > 0.9, which mostly covered the whole evaporation period and the initial contact diameter remained almost constant during evaporation, was targeted. In this range, the previous contact angle functions for the evaporation model underpredicted the experimental data. A new contact angle function of a zircaloy surface was empirically proposed, which represented the present experimental data within a reasonable degree of accuracy.