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Effect of Silicon Content on the Corrosion Resistance and Radiation-Induced Embrittlement of Materials for Advanced Heavy Liquid Metal Nuclear Systems: Quarterly Progress Report (November 2004 – January 2005)

机译:硅含量对先进重液态金属核系统材料耐腐蚀性和辐射致脆性的影响:季度进展报告(2004年11月 - 2005年1月)

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摘要

This proposal is intended to study the effect of Si content not only on the corrosion resistance but also on the radiation-induced embrittlement of martensitic stainless steels. The susceptibility of these alloys with different Si content to stress corrosion cracking, general corrosion and localized corrosion will be evaluated in the molten LBE and aqueous environments of different pH values using state-of-the-art testing techniques. Testing in the aqueous media is intended to develop baseline data for comparison purpose. Radiation-induced embrittlement of these alloys will initially be studied by irradiating the test specimens with bremmstrahlung gamma radiation from 20-40 MeV electron beams at ISU. These gammas induce (γ, n) reactions in the giant dipole energy region. The principal radiation damage from these irradiations, in turn, stems from the recoiling residual nucleus (with average kinetic energy of approximately 20,000 eV) after the neutrons are emitted. The high penetrability of gammas, whose range is of order one meter in steel, ensures that the resulting damage will be uniform over the volume of the sample. The induced activity of these specimens will have very short half-lives (typically minutes) due the systematics of (slightly) proton-rich nuclei. The resulting radiation-induced hardening can subsequently be evaluated by proper experimental techniques.Accomplishments:● Four experimental heats of martensitic alloys (similar to Mod9Cr-1Mo) with different Si content (0.5, 1.0, 1.5 and 2.0 weight percent) have been melted by vacuum-induction melting (VIM) practice at the Timken Research Laboratory.● The VIM heats have been processed into round and rectangular bars, followed by thermal treatments. The heat treatments consisted of austenitizing, quenching, tempering and air cooling to develop a fully-tempered martensitic microstructure in all heats.● Fabrication of test specimens has been initiated.● Literature review on relevant topics is in progress.
机译:该提议旨在研究硅含量不仅对耐腐蚀性的影响,而且对马氏体不锈钢的辐射诱发的脆性的影响。将使用最新的测试技术在熔融的LBE和不同pH值的水性环境中评估这些具有不同Si含量的合金对应力腐蚀开裂,一般腐蚀和局部腐蚀的敏感性。在水性介质中进行测试旨在开发基线数据以进行比较。这些合金的辐射诱发脆化将首先通过在ISU用20-40 MeV电子束的致辐射伽马射线辐照试样来研究。这些伽马在巨偶极能量区中引发(γ,n)反应。这些辐射的主要辐射损害继而来自中子发射后反冲的残留核(平均动能约为20,000 eV)。 γ的高渗透性(范围在钢上约为1米)可确保在样品体积上造成的破坏均匀。由于(少量)富质子核的系统性,这些样品的诱导活性将具有非常短的半衰期(通常为数分钟)。随后可以通过适当的实验技术对由此产生的辐射诱发的硬化进行评估。成就:●熔化了四种Si含量(0.5、1.0、1.5和2.0重量%)的马氏体合金(类似于Mod9Cr-1Mo)的实验热。铁姆肯研究实验室(Timken Research Laboratory)的真空感应熔炼(VIM)实践。●将VIM加热处理为圆棒和矩形棒,然后进行热处理。热处理包括奥氏体化,淬火,回火和空冷,以在所有热量下形成完全回火的马氏体组织。●已开始制造试样。●有关主题的文献综述正在进行中。

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    Roy Ajit K.;

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