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首页> 外文会议>STP 1467; International Symposium on Zirconium in the Nuclear Industry; 20040613-17; Stockholm(SE) >Influence of Structure—Phase State of Nb Containing Zr Alloys on Irradiation-Induced Growth
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Influence of Structure—Phase State of Nb Containing Zr Alloys on Irradiation-Induced Growth

机译：含Nb Zr合金的结构相态对辐照诱导生长的影响

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摘要

On account of the search for the optimal composition and structure-phase state of Zr alloys much attention is paid to upgrade the E110 (Zr-1%Nb) and E635 (Zr-1%Nb-0.35%Fe-1.2%Sn) alloys that have proved well in terms of irradiation-induced creep and growth, high strength characteristics, and corrosion. The difference between the alloy properties is determined by their states related to their compositions. The structure-phase state of the Zr-Nb and Zr-Nb-Fe-Sn systems has been studied after heat treatment in the α-- and α + β- regions and its influence on the irradiation-induced growth (IIG) during BOR-60 irradiation at T = 315-350℃ was investigated. A substantial difference has been shown in the deformation effected by IIG of those alloys; it is less for Zr-Nb-Fe-Sn alloys in dissimilar structure-phase states. The incubation period of the accelerated growth stage is determined by the α-matrix composition, the phase state and the initial dislocation structure. Neutron irradiation leads to a redistribution of alloying elements between the matrix and the precipitates, and to changes in the α-solid solution composition. These changes affect accumulation and mobility of irradiation defects, anisotropy and formation of vacancy c-component dislocation loops. The appearance of c-loops usually correlates with an axial direction acceleration of the IIG of tubes conforming to their texture. The basic regularities of the phase transformation have been established: a) β-Nb precipitates in Zr-Nb alloys are altered in composition to reduce the Nb content from 85-90% to ～ 50%, fine precipitates likely enriched in Nb are formed; b) β-Zr precipitates are subject to irradiation-stimulated decomposition; c) Laves phase precipitates change composition (the content of Fe decreases) and crystal structure, HCP to BCC (β-Nb); d) (Zr,Nb)_2Fe precipitates having the FCC lattice retain their composition and crystal structure; e) no amorphization of any secondary phase precipitates is observable under the given conditions of irradiation (T = 315-350℃). Based on the dpa, the results were compared pertaining to Zr-alloy IIG deformation vs. fluence in various reactors at different energies of fast neutrons. The presented graphs enable comparison between the results of numerous experiments and enable predictions of Zr-material behavior in long-term operation and at high burn-up in commercial reactors.
机译：由于寻求Zr合金的最佳组成和结构相态，因此非常重视升级E110（Zr-1％Nb）和E635（Zr-1％Nb-0.35％Fe-1.2％Sn）合金在辐照引起的蠕变和生长，高强度特性和腐蚀方面已被证明是很好的。合金性能之间的差异取决于它们与组成有关的状态。研究了Zr-Nb和Zr-Nb-Fe-Sn系统的结构相态在α--和α+β-区进行热处理后对BOR过程中的辐射诱导生长（IIG）的影响研究了在T = 315-350℃下的-60辐照。这些合金的IIG产生的变形已显示出很大的差异。 Zr-Nb-Fe-Sn合金的相态不同。加速生长阶段的潜伏期由α-基质组成，相态和初始位错结构决定。中子辐照导致合金元素在基体和沉淀之间重新分布，并导致α-固溶体组成发生变化。这些变化会影响辐照缺陷的积累和迁移，各向异性以及空缺c组分位错环的形成。 c形环的出现通常与符合其纹理的管的IIG的轴向加速度相关。已经建立了相变的基本规律：a）改变Zr-Nb合金中的β-Nb析出物的组成，以将Nb的含量从85-90％降低至〜50％，形成可能富含Nb的细小析出物； b）β-Zr沉淀物受到辐照刺激分解； c）Laves相沉淀改变成分（Fe含量降低）和晶体结构，从HCP到BCC（β-Nb）； d）具有FCC晶格的（Zr，Nb）_2Fe沉淀保留其组成和晶体结构； e）在给定的照射条件下（T = 315-350℃），没有观察到任何次级相沉淀物的非晶化。基于dpa，比较了在快中子不同能量下，各种反应堆中Zr合金IIG变形与注量的结果。所呈现的图使得能够在众多实验的结果之间进行比较，并且能够预测在商用反应器中长期运行和高燃耗时Zr材料的行为。

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