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数据，取自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、核工艺供热项目及区域供热项目），旨在完成候选结构合金在最高950℃服役条件下的合格评定。研究针对每种合金开展了多批次试验，并重点考察服役环境对材料性能的影响：测试环境涵盖含微量杂质气体的氦气（杂质包括氢、水蒸气、一氧化碳及甲烷，分压均为微巴级）以及甲烷重整混合气。试验过程中，上述测试环境会导致试样发生渗碳。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数据均处于同一离散带内。
本数据集被用于制定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（High Temperature Reactor，HTR）结构设计准则研讨会论文集》，作者为G Breitbach、F Schubert、H Nickel，会议编号Jül-Conf-71，1989年4月，刊载于于利希核研究中心有限公司报告（Berichte der Kernforschungsanlage Jülich GmbH，ISSN 0344-5798）。