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ZIRCONIUM BASE ALLOY, FUEL ASSEMBLY FOR WATER-COOLED NUCLEAR POWER REACTOR USING THE SAME, AND CHANNEL BOX

机译:锆基合金,使用相同成分的用于水冷核动力反应堆的燃料组件和通道盒

摘要

PPROBLEM TO BE SOLVED: To prevent corrosion and hydrogen absorption of a zirconium base alloy. PSOLUTION: When it is assumed that a tin concentration, an iron concentration, and a chromium concentration are CSBSn/SB(mass%), CSBFe/SB(mass%), and CSBCr/SB(mass%), respectively, alloy components of the zirconium base alloy to be used for a fuel rod 14, a spacer 17, a water rod 22, or a channel box 23 of a fuel assembly 10 to be loaded into a water-cooled nuclear power reactor satisfy CSBSn/SB1.2, 0.5CSBFe/SB+CSBCr/SB0.8, and 0.26CSBFe/SB/CSBCr/SB1.7, and include one or more elements to be chosen from among vanadium, lanthanum, praseodymium, and germanium. When it is assumed that a total element concentration of four types of elements of vanadium, lanthanum, praseodymium, and germanium is CSBx/SB(mass%), it is desired to satisfy 0.1CSBx/SB0.31. PCOPYRIGHT: (C)2010,JPO&INPIT
机译:

要解决的问题:防止锆基合金腐蚀和吸收氢。

解决方案:假设锡浓度,铁浓度和铬浓度为C Sn (质量%),C Fe (质量%) ,和C Cr (质量%)分别是用于燃料棒14,垫片17,水棒22或燃料电池的通道箱23的锆基合金的合金成分。装入水冷核电反应堆的燃料组件10满足C Sn 1.2、0.5C Fe + C Cr 0.8和0.26 C Fe / C Cr 1.7,并且包括一种或多种选自钒,镧,和锗的元素。当假定钒,镧,和锗的四种元素的总元素浓度为C x (质量%)时,期望满足0.1C x < /SB>0.31。

版权:(C)2010,日本特许厅&INPIT

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