Abstract Capsules containing NaCl–MgCl2 salt with 316L stainless steel or alloy N samples were irradiated in the Ohio State University Research Reactor for 21 nonconsecutive hours. A custom irradiation vessel was designed for this purpose, and details on its design and construction are given. Stainless steel samples that were irradiated during exposure had less corrosive attack than samples exposed to the same conditions without irradiation. Alloy N samples showed no significant effect of irradiation. This work shows a method for conducting in-reactor irradiation–corrosion experiments in static molten salts and presents preliminary data showing that neutron irradiation may decelerate corrosion of alloys in molten chloride salts. Index Terms Molten salt reactor, Corrosion, Irradiation, High-temperature experiment.

中文翻译：

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与熔融氯化物盐接触的合金 N 和 316L 不锈钢的中子辐照

摘要 含有 NaCl-MgCl2 盐和 316L 不锈钢或合金 N 样品的胶囊在俄亥俄州立大学研究反应堆中不连续照射 21 小时。为此目的设计了一个定制的辐照容器，并给出了其设计和构造的详细信息。在暴露期间受到辐照的不锈钢样品比暴露在相同条件下未经辐照的样品具有更少的腐蚀性。合金 N 样品没有显示出显着的辐照效果。这项工作展示了一种在静态熔盐中进行反应堆内辐照腐蚀实验的方法，并提供了初步数据，表明中子辐照可能会减缓合金在熔盐中的腐蚀。索引词 熔盐反应器、腐蚀、辐照、高温实验。