| 法国压水堆燃料元件新一代包壳材料的发展 |
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| 引用本文： | 赵文金. 法国压水堆燃料元件新一代包壳材料的发展[J]. 核动力工程, 2000, 21(3): 278-284 |
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| 作者姓名： | 赵文金 |
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| 作者单位： | 中国核动力研究设计院核燃料及材料国家级重点实验室,成都,610041 |
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| 摘 要： | 概述了法国对核电站燃料元件包壳材料锆合金的开发与研究现状，着重介绍了所开发的新锆合金（Ｍ２，Ｍ３，Ｍ４，Ｍ５合金）在堆内外的性能。其中Ｍ４和Ｍ５合金包过央燃料棒燃耗达到５５ＧＷ．ｄ．ｔ＾－１的辐照考验结果表明，它们的堆内的腐蚀，蠕变和辐照伸长等性能优于改进型Ｚｒ－４合金包壳。
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| 关 键 词： | 法国压水 堆 燃料元件 包壳材料 锆合金 |
Development of New Cladding Materials for PWR Fuel Element in France |
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| Zhao Wenjin. Development of New Cladding Materials for PWR Fuel Element in France[J]. Nuclear Power Engineering, 2000, 21(3): 278-284 |
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| Authors: | Zhao Wenjin |
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| Abstract: | Thedevelopment of PWR fuel element cladding materials in France has been reviewed withreference to the literatures.It is emphasized to introduce the performances in and out ofpile on the new alloys(M2,M3,M4,and M5).The results obtained from irradiation test showthat the corrosion resistance,creep resistance and irradiation growth for M4 and M5 aresuperior to the optimized Zircaloy-4,especially the performances of M5 in and out of pileare much better.Currently,the M5 is being irradiated for sixteenth cycles achieving fuelelement burnups to 63 GW· d/t.The obtained data show that M5 alloy could withstandthe operation condition for fuel element burnups to 65 GW· d/t. |
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| Keywords: | French PWR Fuel element Cladding materials Zirconium alloys Performances in and out of pile |
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