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Corrosion Behavior of Alloys in Molten Fluoride Salts.

机译：合金在熔融氟化盐中的腐蚀行为。

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摘要

The molten fluoride salt-cooled high-temperature nuclear reactor (FHR) has been proposed as a candidate Generation IV nuclear reactor. This reactor combines the latest nuclear technology with the use of molten fluoride salt as coolant to significantly enhance safety and efficiency. However, an important challenge in FHR development is the corrosion of structural materials in high-temperature molten fluoride salt. The structural alloys' degradation, particularly in terms of chromium depletion, and the molten salt chemistry are key factors that impact the lifetime of nuclear reactors and the development of future FHR designs. In support of materials development for the FHR, the nickel base alloy of Hastelloy N and iron-chromium base alloy 316 stainless steel are being actively considered as critical structural alloys. Enriched 27LiF-BeF2 (named as FLiBe) is a promising coolant for the FHR because of its neutronic properties and heat transfer characteristics while operating at atmospheric pressure. In this study, the corrosion behavior of Ni-5Cr and Ni-20Cr binary model alloys, and Hastelloy N and 316 stainless steel in molten FLiBe with and without graphite were investigated through various microstructural analyses.;Based on the understanding of the corrosion behavior and data of above four alloys in molten FLiBe, a long-term corrosion prediction model has been developed that is applicable specifically for these four materials in FLiBe at 700ºC. The model uses Cr concentration profile C(x, t) as a function of corrosion distance in the materials and duration fundamentally derived from the Fick's diffusion laws. This model was validated with reasonable accuracy for the four alloys by fitting the calculated profiles with experimental data and can be applied to evaluate corrosion attack depth over the long-term. The critical constant of the overall diffusion coefficient (Deff) in this model can be quickly calculated from the experimental measurement of alloys' weight loss due to Cr depletion. While many factors affect the Deff such as the grain boundary type, grain size, precipitates, initial Cr concentration as well as temperature, this model provides a methodology for estimating corrosion attack depth of alloys in molten fluoride salts obviating the need for difficult and challenging experiment.
机译：已提出将熔融的氟化物盐冷却的高温核反应堆（FHR）作为候选的IV代核反应堆。该反应堆将最新的核技术与熔融氟化盐用作冷却剂相结合，可显着提高安全性和效率。但是，FHR开发中的一个重要挑战是高温熔融氟化盐中结构材料的腐蚀。结构合金的降解，特别是在铬的消耗方面，以及熔盐的化学性质，是影响核反应堆寿命和未来FHR设计发展的关键因素。为了支持FHR的材料开发，Hastelloy N的镍基合金和316不锈钢的铁铬基合金被积极地认为是关键的结构合金。富集的27LiF-BeF2（称为FLiBe）是FHR的有前途的冷却剂，因为它在大气压下运行时具有中子特性和传热特性。本研究通过各种微观结构分析，研究了Ni-5Cr和Ni-20Cr二元模型合金以及Hastelloy N和316不锈钢在含或不含石墨的熔融FLiBe中的腐蚀行为。根据熔融FLiBe中上述四种合金的数据，开发了长期腐蚀预测模型，该模型特别适用于700ºC时FLiBe中的这四种材料。该模型使用Cr浓度曲线C（x，t）作为材料中腐蚀距离和腐蚀持续时间的函数，该腐蚀距离和腐蚀持续时间基本上是从菲克扩散定律得出的。通过将计算出的轮廓与实验数据拟合，该模型已针对四种合金进行了合理的精度验证，可用于长期评估腐蚀深度。该模型中的总扩散系数（Deff）的临界常数可以通过对实验中由于Cr耗尽引起的合金失重进行快速计算得出。尽管许多因素会影响Deff，例如晶界类型，晶粒尺寸，沉淀，初始Cr浓度以及温度，但该模型提供了一种估算合金在熔融氟化盐中腐蚀腐蚀深度的方法，从而无需进行困难且具有挑战性的实验。

著录项

  • 作者

    Zheng, Guiqiu.;

  • 作者单位

    The University of Wisconsin - Madison.;

  • 授予单位 The University of Wisconsin - Madison.;
  • 学科 Engineering Materials Science.
  • 学位 Ph.D.
  • 年度 2015
  • 页码 187 p.
  • 总页数 187
  • 原文格式 PDF
  • 正文语种 eng
  • 中图分类
  • 关键词

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