Assessment of austenitic stainless steels
Assessment of austenitic stainless steels
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DOI：
10.1016/0920-3796(95)80044-x
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发表时间：
1995-03
影响因子：
1.7
通讯作者：
A. Tavassoli
中科院分区：
文献类型：
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作者：
A. Tavassoli
对不锈钢进行评估是为了推荐最适合 ITER 的结构材料，确定需要额外研究和开发工作以对推荐材料进行全面鉴定和许可的领域，并估算在五年时间表内完成的此类研究和开发计划的成本。在对不同不锈钢类别进行简要评估后，选择范围缩小到奥氏体不锈钢，更准确地说是欧洲保留用于聚变反应堆并用于法国四代快中子增殖反应堆的 316LN 型成分。介绍了推荐钢材的材料规格，结合了从欧洲、日本和美国进行的工作中获得的最新研究和开发成果。可用的数据库是使用从联合中央小组关于 ITER 概要设计的最新报告中提取的边界条件为所选钢材提供的，但也纳入了在初始基本性能阶段或未来扩展性能阶段在这些条件下可能进行的更改。对于每个评估的属性，无论是物理、机械还是环境，都会给出参考值及其相应的趋势曲线，并在适用时提出下限或上限设计曲线。使用未辐照材料的寿命终止特性作为参考设计标准，评估辐照的影响。如果观察到的变化保持在设计中纳入的安全裕度内，则认为它们是可接受的。对于在低于 200 °C 或大约 400 °C 的温度下辐照剂量高达 10 dpa 的材料来说，情况就是如此。如果观察到的变化超过或似乎超过设计中包含的安全裕度，则认为它们是不充分的。在这种情况下，建议进行额外的实验以及适用的安全裕度。确定了无法得出明确结论或缺乏实验数据的领域，并提出了为期五年的研究和开发计划，以建立一个全面的数据库，允许对推荐钢材进行全面鉴定和许可。拟议的研发计划包括计划使用现有的快中子增殖反应堆作为低温辐照手段，以获得大于10 dpa的剂量。
An assessment of stainless steels is performed in order to recommend the most suitable structural material for ITER, to identify areas where additional research and development work is needed for full qualification and licensing of the recommended material, and to estimate the cost of such a research and development programme to be completed within a five year time schedule. After a brief assessment of different stainless steel categories, the choice is narrowed down to austenitic stainless steels, and more precisely to the type 316LN composition retained in Europe for the fusion reactors, and used in four generations of fast breeder reactors in France. Material specifications for the recommended steel are presented, incorporating the most recent research and development results, obtained from work performed in Europe, Japan, and the USA. The available database is presented for the selected steel using the boundary conditions extracted from the most recent report by the Joint Central Team on ITER Outline Design, but also incorporating possible changes that may be made in these conditions either for the initial basic performance phase or for the future extended performance phase. For each evaluated property, whether physical, mechanical or environmental, reference values and their corresponding trend curves are presented and, when applicable, lower bound or upper bound design curves are proposed. Using end-of-life properties of unirradiated materials as the reference design critierion, effects of irradiation are evaluated. If the observed changes remain within the safety margins incorporated in design they are considered acceptable. This is shown to be the case for materials irradiated to doses up to 10 dpa at temperatures either less than 200 °C or around 400 °C. If the observed changes exceed or appear to exceed the safety margins incorporated in design they are considered inadequate. In this case additional experiments, and when applicable safety margins, are recommended. Areas where clear conclusions cannot be drawn, or where there is a lack of experimental data, are identified and a five year research and development programme is proposed for the establishment of a comprehensive database allowing full qualification and licensing of the recommended steel. The proposed research and development programme includes plans to use existing fast breeder reactors as a low temperature irradiation means to obtain doses greater than the 10 dpa.