Test data for uniaxial creep on material INCONEL 617 at 1000 Celsius and a stress of 24 MPa (repeat test)

The Alloy 617 creep rupture data 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 alloy for service at temperatures up to 950°C. Alloy 617 was the prime candidate alloy for construction of the He-He intermediate heat exchanger and hot gas ducting. Several batches and product forms (forged bar, rolled plate, pipes and tubes) of the 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 scatter band at each temperature tested.

The creep rupture tests were carried out in single-specimen and multi-specimen test machines. In the single specimen machines the strain was continuously monitored and strain readings were taken once a day. In the multi-specimen test rigs, there were six strings, each with a different load. There were up to eight test pieces per string and strain measurements were made by interrupting the tests, cooling to room temperature, then measuring the length of each test piece using a travelling microscope. Test interruptions for strain measurements were generally every 1000 h. The tests were carried out according to the German Standard DIN 50118 (1982).

The data (secondary creep rate, time to 1% strain, time to rupture) 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.

In addition to the creep rupture data, Alloy 617 tensile properties, low cycle fatigue and creep crack growth data are stored in MatDB.

本数据集包含617合金（Alloy 617）的蠕变断裂数据，相关试验为配合德意志联邦共和国及北莱茵-威斯特伐利亚州的高温堆（High Temperature Reactor, HTR）项目（包括直接循环氦气轮机项目、核工艺热项目与区域供热项目）开展，旨在评定该合金在最高950℃温度下的服役资格。617合金是氦-氦中间热交换器与热气体导管制造的首选候选合金。研究覆盖该合金的多炉批与多种产品形态（锻棒、轧制板材、管材），并重点关注服役环境对材料性能的影响，这些环境包括含微量（微巴量级）氢、水蒸气、一氧化碳、甲烷等杂质气体的氦气，以及甲烷重整混合气。在试验机内，上述试验环境会导致试样发生渗碳。但数据分析显示，在各试验温度下，空气、含杂质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。

蠕变断裂试验采用单试样与多试样试验机开展。单试样试验机可连续监测应变，且每日采集一次应变读数。多试样试验台包含6个加载通道，每个通道加载载荷各不相同；每个通道最多布置8个试样，应变测量需通过中断试验、冷却至室温后，使用读数显微镜测量各试样长度的方式完成。应变测量的试验中断周期通常为每1000小时一次。所有试验均按照德国标准DIN 50118（1982版）执行。

试验获得的数据（二次蠕变速率、1%应变到达时间、断裂时间）被用于制定高温堆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》（*Proceedings of the Workshop on Structural Design Criteria for HTR*），该文集由G Breitbach、F Schubert、H Nickel编撰，编号为Jül-Conf-71，出版于1989年4月，隶属于于利希研究中心报告系列（Berichte der Kernforschungsanlage Jülich GmbH），国际标准刊号ISSN 0344-5798。

除蠕变断裂数据外，617合金的拉伸性能、低周疲劳与蠕变裂纹扩展数据亦存储于材料数据库（MatDB）中。