Test data for uniaxial creep on material INCONEL 617 at 800 Celsius and a stress of 55.01 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.

本数据集包含617合金（Alloy 617）的蠕变断裂数据（creep rupture data），相关试验为德意志联邦共和国及北莱茵-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、核工艺热项目及区域供热项目）开展，旨在使该合金获得最高950℃服役工况下的使用资质。617合金是氦-氦中间热交换器与热气体导管的首选候选合金。研究人员对该合金的多炉批次及多种产品形态（锻棒、轧制板材、管材）进行了试验，并重点关注服役环境对材料性能的影响，这些环境包括含微巴级杂质气体（氢气、水蒸气、一氧化碳、甲烷）的氦气，以及甲烷重整混合气。试验过程中，上述环境会导致试样发生渗碳。但数据分析表明，各试验温度下，空气、不纯氦气及甲烷重整气中的应力断裂数据均处于同一分散带内。

蠕变断裂试验采用单试样试验机与多试样试验机开展。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。多试样试验台设有6组加载工况各异的串列试样组，每组最多包含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。所有试验均依据德国标准DIN 50118（1982）进行。

试验所得数据（二次蠕变速率、1%应变对应时间、断裂时间）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《高温反应堆结构设计准则研讨会论文集》（"Proceedings of the Workshop on Structural Design Criteria for HTR"），作者为G Breitbach、F Schubert、H Nickel，会议编号Jül-Conf-71，出版于1989年4月，由于利希核研究中心有限公司（Berichte der Kernforschungsanlage Jülich GmbH）发行，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、低周疲劳及蠕变裂纹扩展数据均存储于MatDB中。