N36锆合金包壳堆内腐蚀模型研究
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摘要
本文利用池边检查数据,基于阿累尼乌斯方程建立了N36锆合金包壳堆内腐蚀最佳估算模型。由于缺乏腐蚀转折前数据,N36锆合金包壳腐蚀转折前氧化膜厚度只是时间的函数,腐蚀转折后氧化膜厚度是包壳温度和时间的函数。通过在最佳估算腐蚀模型上添加工程因子,建立了不同加工工艺N36锆合金包壳腐蚀模型。N36锆合金包壳腐蚀包络模型在最小腐蚀转折点的基础上建立。模型验证结果表明,N36锆合金包壳腐蚀模型与验证数据符合较好,能够用于N36锆合金堆内腐蚀行为模拟。
In this paper,the best estimation in-pile corrosion model of N36 zirconium alloy cladding was established based on the Arrhenius equation by using the poolside examination data.Due to the lack of corrosion data before corrosion transition,N36 zirconium alloy cladding corrosion model before corrosion transition was only a function of time,while the corrosion model after corrosion transition was a function of cladding temperature and time.N36 zirconium alloy cladding corrosion model was established by adding engineering factors to the best estimation corrosion model.N36 zirconium alloy cladding corrosion bound model was established based on minimum corrosion transition point.The results show that the N36 zirconium alloy cladding corrosion model agrees well with the verification data and can be used for the simulation of N36 zirconium alloy cladding corrosion behavior in reactor.
In this paper,the best estimation in-pile corrosion model of N36 zirconium alloy cladding was established based on the Arrhenius equation by using the poolside examination data.Due to the lack of corrosion data before corrosion transition,N36 zirconium alloy cladding corrosion model before corrosion transition was only a function of time,while the corrosion model after corrosion transition was a function of cladding temperature and time.N36 zirconium alloy cladding corrosion model was established by adding engineering factors to the best estimation corrosion model.N36 zirconium alloy cladding corrosion bound model was established based on minimum corrosion transition point.The results show that the N36 zirconium alloy cladding corrosion model agrees well with the verification data and can be used for the simulation of N36 zirconium alloy cladding corrosion behavior in reactor.
引文
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[3]SCDAP/RELAP5-3D Code Development Team.SCDAP/RELAP5-3D code manual,Volume 4:MATPRO:A library of material properties for light-water-reactor accident analysis,Revision2.2[R].USA:Idaho National Laboratory,2003.
[4]庞华,译.COCCINEL计算机程序用户手册[R].成都:中国核动力研究设计院,1993.
[5]JACOUD J L,VESCO P.Description and qualification of the Copernic[C]∥Fuel Rod Design Code.[S.l.]:[s.n.],2000.
[6]KONKOV V,SABLIN M,KHOKHUNOVA T,et al.Assessment of E110and E635alloy corrosion behavior in VVER-1200reactors[EB/OL].http:∥library.sinap.ac.cn/db/hedianwencui201101/%C8%AB%CE%C4/41081166.pdf.
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