Test data for uniaxial creep on material INCONEL 617 at 900 Celsius and a stress of 58.46 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.

本数据集收录的617合金（Alloy 617）蠕变断裂数据（creep rupture data），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项目——包括直接循环氦气涡轮机项目、核工艺热项目及区域供热项目，旨在评定该合金在最高950℃工况下的服役资格。617合金是氦-氦中间热交换器（He-He intermediate heat exchanger）与热气体管道（hot gas ducting）建造的首选候选合金。本试验针对该合金的多炉批及多种产品形态（锻棒、轧制板材、管材与管件）开展研究，并重点考察服役环境对其性能的影响：服役环境涵盖含微量杂质气体的氦气（杂质包括氢、水蒸气、一氧化碳与甲烷，均为微巴级别）以及甲烷重整混合气。在试验设备中，上述试验环境会引发试样渗碳（carburisation）。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试验机（single-specimen test machines）与多试样试验机（multi-specimen test machines）开展。单试样试验机可对应变进行连续监测，并每日记录一次应变读数。多试样试验台（multi-specimen test rigs）共设六组加载串，每组搭载不同载荷，单组最多可放置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（travelling microscope）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版）执行。

本次采集的数据包含二次蠕变速率（secondary creep rate）、1%应变到达时间（time to 1% strain）与断裂时间（time to rupture），用于起草高温反应堆系统的核设计规范草案，相关内容总结于《高温堆（High Temperature Reactor, HTR）结构设计准则研讨会论文集》，作者为G Breitbach、F Schubert与H Nickel，会议编号Jül-Conf-71，发表于1989年4月，收录于《于利希核研究中心报告》（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（Alloy 617）的拉伸性能（tensile properties）、低周疲劳（low cycle fatigue）与蠕变裂纹扩展数据（creep crack growth data）均存储于MatDB数据库（MatDB）。