Creep dataset from peer-reviewed literature of nuclear structural materials

The dataset provides records of creep properties for structural materials used in nuclear applications, focusing on the influence of specimen dimensions on time-dependent deformation behavior. It was developed through an extensive literature search of peer-reviewed articles, technical reports, and institutional databases, including contributions from 50 publications and databases. The search targeted studies presenting quantitative creep data for both standard and sub-sized specimens, with detailed information on testing conditions, specimen geometries, and material compositions. The compiled database contains 1,413 creep testing records covering parameters that include alloy type and grade, chemical composition, thermal and mechanical treatment history, irradiation conditions, specimen geometry and dimensions, and measured creep properties. The dataset encompasses material classes such as stainless steels (A709, SS304, SS316), reactor pressure vessel steels (SA533, SA508), nickel-based alloys (IN600, IN617), and zirconium alloys (Zr-2, Zr-3, Zr-4). Experts in materials science reviewed and validated all records, verifying material specifications, treatment conditions, and testing parameters for consistency and accuracy.

本数据集收录了核应用领域结构材料的蠕变性能（creep properties）记录，重点研究试样尺寸（specimen dimensions）对材料时变变形行为的影响。本数据集通过对同行评议论文、技术报告及机构数据库的全面文献检索构建完成，共纳入50种出版物与数据库的相关数据。本次检索靶向覆盖了提供标准试样与亚尺寸试样定量蠕变数据的研究，且包含试验条件、试样几何参数及材料成分等详细信息。本汇编数据库共包含1413条蠕变试验记录，涵盖的参数包括合金类型与牌号、化学成分、热机械处理历程、辐照条件、试样几何参数与尺寸，以及实测蠕变性能。本数据集涵盖的材料类别包括不锈钢（A709、SS304、SS316）、反应堆压力容器钢（SA533、SA508）、镍基合金（IN600、IN617）以及锆合金（Zr-2、Zr-3、Zr-4）。材料科学领域专家对所有记录进行了审核与验证，核查了材料规格、处理条件及试验参数的一致性与准确性。