Test data for uniaxial tensile on material ALLOY 800H at 20 Celsius

The creep rupture data in this collection were determined for the high temperature reactor projects (the direct cycle helium turbine project, the nuclear process heat project and the district heating project) of the Federal Republic of Germany and the State of North Rhine Westphalia, the aim being to qualify the candidate constructional alloys for service at temperatures up to 950°C. Several batches of each alloy were investigated and special attention was given to the effects of the service environments (helium containing different impurity gases, such as hydrogen, water vapour, carbon monoxide and methane, all at microbar levels, and methane reforming gas mixture) on the properties. In the test machines, these test environments led to carburisation of test pieces. However, analysis of the data showed that the stress rupture data for tests in air, in impure helium and in methane reforming gas lay in the same scatterband at each temperatures tested.

The data were used for the formulation of draft nuclear design rules for the high temperature reactor systems, which are summarised in 'Proceedings of the Workshop on Structural Design Criteria for HTR', G Breitbach, F Schubert, H Nickel, Jül-Conf-71, April 1989, Berichte der Kernforschungsanlage Jülich GmbH, ISSN 0344-5798.

本数据集收录的蠕变断裂数据（creep rupture data），系为德意志联邦共和国及北莱茵-威斯特法伦州的高温反应堆项目（high temperature reactor projects）——包括直接循环氦气轮机项目（direct cycle helium turbine project）、核工艺供热项目（nuclear process heat project）及区域供热项目（district heating project）——所测定，旨在评定候选结构合金（candidate constructional alloys）在最高950°C温度下的服役适用性。针对每种合金的多批次试样展开研究，并重点关注服役环境（service environments）——包括含不同杂质气体（如氢气、水蒸气、一氧化碳及甲烷，均为微巴级浓度）的氦气，以及甲烷重整气体混合物（methane reforming gas mixture）——对材料性能的影响。在试验机中，这些试验环境导致试样发生渗碳（carburisation）。

该数据被用于高温反应堆系统（high temperature reactor systems）核设计规则草案（draft nuclear design rules）的制定，相关内容总结于《高温反应堆结构设计准则研讨会论文集》（Proceedings of the Workshop on Structural Design Criteria for HTR），作者为G Breitbach、F Schubert、H Nickel，文献编号Jül-Conf-71，1989年4月，载于于利希核研究中心报告（Berichte der Kernforschungsanlage Jülich GmbH），ISSN 0344-5798。