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Zr—1%Nb合金管在冲击载荷作用下的屈服极限
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作者 黄金昌 《稀有金属快报》 CSCD 1998年第6期4-5,共2页
关键词 zr-1%nb合金管 合金 冲击载荷 屈服极限
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微量氧环境下热处理温度对Zr-1%Nb合金力学性能的影响
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作者 刘洋 赵亚欢 +3 位作者 龚恒风 王占伟 廖业宏 任啟森 《材料热处理学报》 EI CAS CSCD 北大核心 2021年第3期89-93,共5页
采用扫描电镜、X射线衍射仪及万能试验机等研究了微量氧环境下400、800和1200℃不同温度保温300 s对Zr-1%Nb合金力学性能的影响。结果表明:与未热处理的合金相比,400℃热处理后Zr-1%Nb合金的力学性能未发生明显变化;800℃热处理后,合金... 采用扫描电镜、X射线衍射仪及万能试验机等研究了微量氧环境下400、800和1200℃不同温度保温300 s对Zr-1%Nb合金力学性能的影响。结果表明:与未热处理的合金相比,400℃热处理后Zr-1%Nb合金的力学性能未发生明显变化;800℃热处理后,合金的塑性降低,压缩时外表面产生大量微裂纹;1200℃热处理后,压缩时合金出现了脆性断裂。热处理后合金样品的表面发生了氧化,氧化产物主要为ZrO2相。随着热处理温度的升高,Zr-1%Nb合金的氧化程度逐步加深,并且1200℃热处理后试样氧化层的厚度显著增加,内部出现大量裂纹。 展开更多
关键词 zr-1%nb合金 热处理 塑性 氧化产物
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Multiphysics simulation of VVER-1200 fuel performance during normal operating conditions 被引量:2
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作者 Khaled M.Yassin Mohamed H.Hassan +3 位作者 Mohammad M.Ghoneim Mostafa S.Elkolil Adel Alyan Said A.Agamy 《Nuclear Science and Techniques》 SCIE EI CAS CSCD 2023年第2期139-152,共14页
Nuclear fuel performance modeling and simulation are critical tasks for nuclear fuel design optimization and safety analysis under normal and transient conditions.Fuel performance is a complicated phenomenon that invo... Nuclear fuel performance modeling and simulation are critical tasks for nuclear fuel design optimization and safety analysis under normal and transient conditions.Fuel performance is a complicated phenomenon that involves thermal,mechanical,and irradiation mechanisms and requires special multiphysics modules.In this study,a fuel performance model was developed using the COMSOL Multiphysics platform.The modeling was performed for a 2D axis-symmetric geometry of a UO2fuel pellet in the E110 clad for VVER-1200 fuel.The modeling considers all relevant phenomena,including heat generation and conduction,gap heat transfer,elastic strain,mechanical contact,thermal expansion,grain growth,densification,fission gas generation and release,fission product swelling,gap/plenum pressure,and cladding thermal and irradiation creep.The model was validated using a code-to-code evaluation of the fuel pellet centerline and surface temperatures in the case of constant power,in addition to validation of fission gas release(FGR)predictions.This prediction proved that the model could perform according to previously published VVER nuclear fuel performance parameters.A sensitivity study was also conducted to assess the effects of uncertainty on some of the model parameters.The model was then used to predict the VVER-1200 fuel performance parameters as a function of burnup,including the temperature profiles,gap width,fission gas release,and plenum pressure.A compilation of related material and thermomechanical models was conducted and included in the modeling to allow the user to investigate different material/performance models.Although the model was developed for normal operating conditions,it can be modified to include off-normal operating conditions. 展开更多
关键词 VVER-1200 Fuel performance COMSOL code zr-1%nb cladding UO2 fuel rod
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