Test data for uniaxial creep on material INCONEL 617 at 900 Celsius and a stress of 17 MPa

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.

本数据集所收录的617合金蠕变断裂（creep rupture）数据，源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（high temperature reactor）项目，包括直接循环氦气轮机项目、核工艺热项目以及区域供热项目，旨在验证该合金可在最高950℃的工况下服役。617合金是He-He中间热交换器与热气体管道建造的首选候选合金。

研究覆盖了该合金的多个批次与多种产品形态，包括锻造棒材、轧制板材、管材与管件，并重点考察了服役环境对其性能的影响：服役环境包含含微量杂质气体（氢、水蒸气、一氧化碳、甲烷，分压均为微巴级别）的氦气，以及甲烷重整混合气体。在试验设备中，上述试验环境会导致试样发生渗碳（carburisation）现象。但数据分析结果显示，在各试验温度下，空气环境、不纯氦气环境与甲烷重整气体环境下的应力蠕变断裂数据均处于同一离散带内。

蠕变断裂试验分为单试样试验机与多试样试验台两种方式开展。单试样试验机中，应变被连续监测，且每日采集一次应变读数。多试样试验台共包含6组加载串，每组加载串施加不同的载荷，每组最多可搭载8个试样。应变测量需通过中断试验、冷却至室温后，使用移动式显微镜测量每个试样的长度来完成。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。

本数据集包含的蠕变第二阶段速率、达到1%应变的时间以及断裂时间数据，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《高温气冷堆（HTR, High Temperature Reactor）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，发表于《于利希核研究中心报告集》（Berichte der Kernforschungsanlage Jülich GmbH），ISSN 0344-5798。

除蠕变断裂数据外，MatDB数据库中还存储了617合金的拉伸性能、低周疲劳（low cycle fatigue）以及蠕变裂纹扩展数据。