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Radiation damage to aluminum and aluminum alloys.

机译:辐射损坏铝和铝合金。

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摘要

An evaluation of proton and neutron damage to aluminum and various aluminum alloys has been performed. The proton studies were conducted at energies of 200-MeV, 800-MeV, and 23.5 GeV. The proton studies consisted of evaluation and characterization of proton irradiated window/target materials from accelerators and comparison to non-irradiated archival materials. The materials evaluated for the proton irradiations included 99.9999 wt% aluminum, 1100 aluminum, and 5052 aluminum. The neutron damage research centered on 6061 T-6 aluminum which was obtained from a control rod follower from the Brookhaven National Laboratory's (BNL) High Flux Beam Reactor (HFBR). This material had received thermal neutron fluence up to {dollar}spsim{dollar}4 {dollar}times{dollar} 10{dollar}sp{lcub}23{rcub}{dollar} n/cm{dollar}sp2{dollar}. It is shown that the large increases in tensile strength with decreasing elongation and notch impact resistance can be attributed to the development of a precipitate of amorphous silicon in the alloy matrix. This precipitate is produced radiogenically and approaches 8 wt%. The precipitate can be transformed into a crystalline structure with applied heat treatment. The nucleation of this amorphous phase is discussed and the spherical shape of the silicon precipitate is evaluated. The effects of thermal-to-fast neutron flux ratios are also discussed. The increases in tensile strength in the proton irradiated materials is shown to be the result of atomic displacements. These displacements cause interstitials which aggregate into defect clusters which result in radiation hardening of the materials. The size and effects of displacement cascades are considered relative to the hardening of the aluminum alloy. Production of gas (helium) in the grain boundaries of proton irradiated 99.9999 wt% aluminum and the potential for liquid metal embrittlement are reviewed. The metallurgical and mechanical property evaluations for the research consisted of electron microscopy (both scanning and transmission), X-ray diffraction, tensile testing, microhardness testing, Charpy impact testing and single-sided notch tensile testing.
机译:质子和中子对铝和各种铝合金的损坏已经进行了评估。质子研究是在200MeV,800MeV和23.5 GeV的能量下进行的。质子研究包括评估和表征来自加速器的质子辐照窗/目标材料,并与非辐照档案材料进行比较。质子辐照评估的材料包括99.9999 wt%的铝,1100铝和5052铝。中子损伤研究以6061 T-6铝为中心,该铝是从布鲁克海文国家实验室(BNL)的高通量束反应堆(HFBR)的控制棒随动件获得的。该材料受到的热中子通量达{dolsp} spsim {dollar} 4 {dollar} times {dollar} 10 {dollar} sp {lcub} 23 {rcub} {dollar} n / cm {dollar} sp2 {dollar}。结果表明,拉伸强度随伸长率的降低而大幅度增加,并且缺口抗冲击性可以归因于合金基质中非晶硅沉淀的发展。该沉淀物是放射线产生的并且接近8重量%。可以通过施加热处理将沉淀物转变成晶体结构。讨论了该非晶相的成核作用,并评估了硅沉淀物的球形。还讨论了热对中子通量比的影响。质子辐照材料中抗张强度的增加表明是原子位移的结果。这些位移导致间隙聚集到缺陷簇中,从而导致材料的辐射硬化。位移级联的大小和影响是相对于铝合金的硬化而言的。综述了质子辐照的99.9999 wt%的铝在晶界中的气体(氦)的产生以及液态金属脆化的可能性。该研究的冶金和机械性能评估包括电子显微镜(扫描和透射),X射线衍射,拉伸测试,显微硬度测试,夏比冲击测试和单面缺口拉伸测试。

著录项

  • 作者

    Czajkowski, Carl Joseph.;

  • 作者单位

    State University of New York at Stony Brook.;

  • 授予单位 State University of New York at Stony Brook.;
  • 学科 Engineering Materials Science.; Physics Radiation.
  • 学位 Ph.D.
  • 年度 1996
  • 页码 239 p.
  • 总页数 239
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类 工程材料学;原子核物理学、高能物理学;
  • 关键词

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