Silicon carbide fiber reinforced silicon carbide matrix(SiC_(f)/SiC)composite is the key cladding material of nuclear fuel,which determines the safety and reliability of nuclear fuel storage and transportation.The rep...Silicon carbide fiber reinforced silicon carbide matrix(SiC_(f)/SiC)composite is the key cladding material of nuclear fuel,which determines the safety and reliability of nuclear fuel storage and transportation.The replacement of its storage and transportation scenario needs to be completed by the manipulator,but the application of SiC_(f)/SiC wear,fracture,and nuclear leakage in the snatching process of brittle-flexible-rigid contact in the irradiation environment has been seriously restricted due to unclear understanding of the damage mechanism.Therefore,the effects of irradiation dose and clamping load on the friction characteristics of the contact interface between SiC_(f)/SiC clad tube are studied in this paper,and the effects of irradiation parameters and clamping force on the static friction coefficient of the contact interface between the clad tube and flexible nitrile are obtained.Based on the Greenwood-Williamson tribological model,a numerical model of the shape and structure of the contact micro-convex at the micro-scale of the clamping interface is constructed by introducing the multi-surface integral,and finally verified by experiments.The research results show that there is a unique“Irradiation suppression zone”under the clamping condition of SiC_(f)/SiC cladding tube under the nuclear irradiation environment,and the growth of static friction coefficient slows down until stagnates after irradiation reaches a certain extent(600 kGy),and there will be a decline when the irradiation dose continues to increase,among which the clamping force of 15.2 N within the irradiation interval of 1,000 kGy can meet the safety of nuclear environment operation.The results of this paper can provide an important theoretical basis and application guidance for the safe operation of SiC_(f)/SiC cladding tubes in the storage and transportation clamping process.展开更多
为了提高锆合金包壳管的冷轧质量,通过统计过程控制技术和工序能力分析研究了锆合金包壳管冷轧后的壁厚偏差问题,并基于试验设计(design of experiment, DOE)技术对皮格尔冷轧工艺进行了优化。包壳管冷轧质量分析和工艺优化试验的结果表...为了提高锆合金包壳管的冷轧质量,通过统计过程控制技术和工序能力分析研究了锆合金包壳管冷轧后的壁厚偏差问题,并基于试验设计(design of experiment, DOE)技术对皮格尔冷轧工艺进行了优化。包壳管冷轧质量分析和工艺优化试验的结果表明,轧制前管材的壁厚偏差和送进量对轧制后的管材壁厚偏差有显著影响;当轧制前管材壁厚偏差<0.3 mm、壁厚变形量为65%、送进量为1.0 mm/次时,轧制后的管材壁厚偏差最小;通过轧制工艺优化后,反映壁厚偏差离散性的极差平均值由0.036减小到0.018,极差波动也明显减小,轧制质量显著提高;当轧制管材壁厚变形量一定时,对轧制前壁厚偏差较大的管材,采用小送进量轧制,可减小轧制后管材的壁厚偏差,达到提高锆合金包壳管材质量的目的。展开更多
基金supported by the National Natural Science Foundation of China(Grant No.52075526)the“Ningbo 3315 Plan Innovation Team”(Grant No.2017A-28-C)+2 种基金the National Natural Science Foundation of China(Grant No.91860204)the Fundamental Research Funds for the Central Universities(Grant No.DUT22LAB605)the National Key R&D Program of China(Grant No.2018YFB1107500).
文摘Silicon carbide fiber reinforced silicon carbide matrix(SiC_(f)/SiC)composite is the key cladding material of nuclear fuel,which determines the safety and reliability of nuclear fuel storage and transportation.The replacement of its storage and transportation scenario needs to be completed by the manipulator,but the application of SiC_(f)/SiC wear,fracture,and nuclear leakage in the snatching process of brittle-flexible-rigid contact in the irradiation environment has been seriously restricted due to unclear understanding of the damage mechanism.Therefore,the effects of irradiation dose and clamping load on the friction characteristics of the contact interface between SiC_(f)/SiC clad tube are studied in this paper,and the effects of irradiation parameters and clamping force on the static friction coefficient of the contact interface between the clad tube and flexible nitrile are obtained.Based on the Greenwood-Williamson tribological model,a numerical model of the shape and structure of the contact micro-convex at the micro-scale of the clamping interface is constructed by introducing the multi-surface integral,and finally verified by experiments.The research results show that there is a unique“Irradiation suppression zone”under the clamping condition of SiC_(f)/SiC cladding tube under the nuclear irradiation environment,and the growth of static friction coefficient slows down until stagnates after irradiation reaches a certain extent(600 kGy),and there will be a decline when the irradiation dose continues to increase,among which the clamping force of 15.2 N within the irradiation interval of 1,000 kGy can meet the safety of nuclear environment operation.The results of this paper can provide an important theoretical basis and application guidance for the safe operation of SiC_(f)/SiC cladding tubes in the storage and transportation clamping process.
