Test data for uniaxial creep on material ALLOY 800H at 850 Celsius and a stress of 20 MPa

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（creep rupture）数据，源自德意志联邦共和国及北莱茵-威斯特伐利亚州的高温反应堆项目（含直接循环氦气涡轮机项目、核工艺热项目与区域供热项目），旨在评定候选结构合金在最高950℃服役温度下的适配性能。针对每种合金开展了多炉批号试验，并重点考察了服役环境对材料性能的影响：试验环境包括含氢、水蒸气、一氧化碳、甲烷等微巴级微量杂质气体的氦气，以及甲烷重整混合气体。试验过程中，上述环境会导致试样发生渗碳。但数据分析表明，在各试验温度下，空气、不纯氦气及甲烷重整气体环境下的应力断裂（stress rupture）数据均处于同一离散带内。
本数据集用于制定高温反应堆（High Temperature Reactor，缩写HTR）系统的核设计规范草案，相关内容总结于《高温堆结构设计准则研讨会论文集》（作者：G Breitbach、F Schubert、H Nickel，会议编号Jül-Conf-71，1989年4月，于利希核研究有限公司（Kernforschungsanlage Jülich GmbH）报告系列，ISSN 0344-5798）。