Test data for low cycle fatigue - strain control on material ALLOY 800H at 850 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（creep rupture）数据，均为德意志联邦共和国与北莱茵-威斯特伐利亚州的高温反应堆项目（含直接循环氦气轮机项目、核工艺热项目及区域供热项目）所测定，旨在为最高服役温度达950℃的候选结构合金完成服役资格认证。针对每种合金，研究团队开展了多炉批次的试验，并重点考察了服役环境对材料性能的影响：这些环境包括含微巴量级杂质气体（如氢气、水蒸气、一氧化碳与甲烷）的氦气，以及甲烷重整混合气。在试验设备中，上述试验环境会引发试样渗碳。但数据分析显示，在各测试温度下，空气、不纯氦气及甲烷重整气环境下的应力断裂（stress rupture）数据均处于同一离散带内。
本数据集被用于起草高温反应堆系统的核设计规范草案，相关内容总结于《高温反应堆（HTR）结构设计准则研讨会论文集》，编者为G Breitbach、F Schubert、H Nickel，会议编号Jül-Conf-71，1989年4月，载于于利希核研究中心有限公司报告集，国际标准刊号ISSN 0344-5798。