Test data for uniaxial tensile on material ALLOY 800H irr at 600 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，源自德意志联邦共和国与北莱茵-威斯特法伦州的高温反应堆项目（包括直接循环氦气涡轮机项目、核工艺供热项目及区域供暖项目），旨在对候选结构合金进行资质认定，以验证其能否在高达950°C的温度下服役。对每种合金的多批次样品进行了研究，并重点关注服役环境（含不同杂质气体的氦气——如氢气、水蒸气、一氧化碳和甲烷，均为微巴级浓度——以及甲烷重整气体混合物）对材料性能的影响。在试验设备中，这些试验环境导致试样发生渗碳。然而，数据分析表明，在空气、不纯氦气及甲烷重整气体环境下的应力断裂数据，在各测试温度下均处于同一分散带内。

该数据集被用于制定高温反应堆系统的核设计规则草案，相关内容已汇总于《高温反应堆（HTR）结构设计准则研讨会论文集》（G Breitbach、F Schubert、H Nickel编著，Jül-Conf-71，1989年4月，于利希核研究中心报告，ISSN 0344-5798）。